EA024235B1 - Methods and systems for migrating fuel assemblies in a nuclear fission reactor - Google Patents

Abstract

Illustrative embodiments provide methods and systems for migrating fuel assemblies in a nuclear fission reactor, methods of operating a nuclear fission traveling wave reactor, methods of controlling a nuclear fission traveling wave reactor, systems for controlling a nuclear fission traveling wave reactor, computer software program products for controlling a nuclear fission traveling wave reactor, and nuclear fission traveling wave reactors with systems for migrating fuel assemblies.

Description

The present invention relates to methods and systems for moving fuel assemblies in a nuclear fission reactor.

Cross references to related applications

This application relates (and claims benefits from them) to the earliest available valid date (s) for filing the following listed applications (hereinafter referred to as related applications), for example, claims the earliest available priority dates for other patent applications, except for preliminary , or claims benefits in accordance with 35 I8C § 119 (e) for provisional patent applications for any and all generic applications of a related application (related applications). The subject of related applications and any and all generic applications of related applications fully by reference includes in this description to the extent that this subject is consistent with this description.

Related Applications

For purposes not covered by the requirements of the United States Patent and Trademark Office υδΡΤΟ, this application is a partial continuation of U.S. Patent Application No. 12/590448, entitled ΜΕΤΗΟΌδ ΑΝΌ δΥδΤΕΜδ ROCK ΜΙΟΚΑΤΙΝΟ РиЕЬ ΑδδΕΜΒΕΙΕδ ΙΝ Α ΝυСЬЕАК ΡΙδδΙΟΝ ΚΕΑСΤОάι сппіпппіпр. Kobepek Α. Nube, Ko'ei S. Re1gohkk LhNia S. ^ abeg, Lutah ΑΙΙαη Husaueg CHag1ex ^ béteg, botee11 b. ^ oob, L and Oeogde Β. 21sttag are named as inventors, filed November 6, 2009, which is currently being considered or is an application, simultaneously considered with which the application has the right to priority by filing date.

For purposes not covered by υδΡΤΟ requirements, this application is a partial continuation of U.S. Patent Application No. 12/657725 entitled ΜΕΤΗΟΌδ ΑΝΌ δΥδΤΕΜδ ROCK ΜΙΟΚΑΤΙΝΟ ΜΙΟΚΑΤΙΝΟυΕΌ ΑδδΙΝδ ΙΝ Α ΜΧΕΕΑΡ ΡΙδδΙΟΝ ΚΕΑΟΓΟΚ, in which ΕΠικΙ Ogeeraprap, Kobepek Α. Nube, Ko'ei S. RePohkk. TohNia S. ^ ayeg, Lutah ^ oob, L and Oeogde Β. The 21st companies are named as inventors, filed on January 25, 2010, which is currently being considered or is an application at the same time being considered with which the application is entitled to priority by filing date.

For purposes not covered by the υδΡΤΟ requirements, this application is a partial continuation of U.S. Patent Application No. 12/657726 entitled ΜΕΤΗΟΌδ ΑΝΏ δΥδΤΕΜδ ΡΟΚ ΜΉ ^ ΤΕ ^ ΡυΕΌ ΑδδΕΜΒΕΙΕδ ΙΝ Α ΜΧΕΙ / ΑΡ ΡΙδδΙΟΝ ΤΟΚC которой, in which ΕΠικΙ Ohiepehrap, Kobek. Nuba, Koje S. RePohkk 1ohkia S. ^ ayeg, Lutah Α1Ειπ ^ еуег, Ska1eh νίΦικο Ьотее11 b. Vοοб, Л and Оеогде Β. The 21st companies are named as inventors, filed on January 25, 2010, which is currently being considered or is an application at the same time being considered with which the application is entitled to priority by filing date.

For purposes not covered by υδΡΤΟ requirements, this application is a partial continuation of U.S. Patent Application No. 12/657735 entitled ΜΕΤΗΟΌδ ΑΝΏ δΥδΤΕΜδ ΡΟΚ ΤΕ ^ ΤΕ ^ ΡυΕΌ ΑδδΕΜΒΕΙΕδ ΙΝ Α ΜΧΕΙ / ΑΡ ΡΙδδΙΟΝ ΚΕΑCΚΕΑ, in which ΕΠικΙ Ohiepekhrap, Kobek. ^ be, Köy S. Reiohkk 1okhkia S. \ νη1 ^ Γ, Lyutakh Α1Ειπ Vеаνе ^, Skag1ekh νίΦικο Ьотее11 b. Vοοб, Л and Оеогде Β. The 21st companies are named as inventors, filed January 25, 2010, which is currently being considered at the same time, or is an application at the same time being considered with which the application is entitled to priority by filing date.

The United States Patent and Trademark Office υδΡΤΟ has published a notice stating that υδ компьютер computer programs require applicants to reference the serial number of the application and indicate whether the application is a continuation, partial continuation or division of a patent application. See δ ^ ρίκπ O. Kishi, Βepeyΐ oG RPog-RPeb Αrr1 ^ saΐ ^ οп, υδΡΤΟ ΟΓΓίοίη1 Оа / еПе ЛагЭН 18, 2003. The current applicant entity (hereinafter referred to as the Applicant) provided the above-mentioned specific link to the application , according to which claims are claimed for priority in accordance with the requirements of the law. Applicant understands that the law is unambiguous in its particular conditional language and does not require either a serial number for the application or any description, such as a continuation or partial continuation, to claim priority over US patent applications. Notwithstanding the foregoing, the applicant understands that the computer programs υδΡΤΟ impose certain requirements for data entry, and therefore the applicant provided a designation (s) of the relationship between the current application and its patrimonial application (s), indicated (indicated) above, but in a positive way notes that these designations should in no case be construed as any type of explanation and (or) assumption as to whether this application contains or does not contain any new material in addition to the material of her generic application (s).

SUMMARY OF THE INVENTION

The examples of illustrative embodiments provide methods and systems for moving fuel assemblies in a nuclear fission reactor, methods for operating a traveling wave nuclear reactor, methods for controlling a traveling wave reactor, systems for controlling a traveling wave nuclear reactor, computer software products for controlling a traveling-wave nuclear reactor and traveling-wave nuclear reactors with systems for moving fuel assemblies.

The above brief description is merely illustrative and is not intended in any way to limit the scope of the present invention. In addition to the illustrative aspects, embodiment, and features described above, from the graphic material and the following detailed description, further aspects, embodiments, and features will become apparent.

A brief description of the graphic material

FIG. 1A is a flowchart of an illustrative method for operating a traveling wave nuclear reactor; FIG. 1Β-1Ό are perspective views in partially schematic form of components of illustrative core areas of a nuclear reactor, FIG. 1E-1H illustrate the effect on the shape of the combustion front of a traveling wave of nuclear fission of the displacement of selected fuel fission subassemblies of nuclear fission, FIG. 11 is a flowchart of a detail of a part of the method of FIG. 1A, FIG. H illustrates the rotation of a nuclear fission fuel subassembly, FIG. 1K is a flowchart of a detail of a part of the method of FIG. 1A, FIG. 1b illustrates the inversion of a nuclear fission fuel subassembly; FIG. 1Μ-1Ν are flowcharts of a detail of a part of the method of FIG. 1A, FIG. 10 illustrates the helical movement of a nuclear fission fuel subassembly; FIG. 1P is a flowchart of a detail of a part of the method of FIG. 1A, FIG. 10 illustrates axial movement of a nuclear fission fuel subassembly; FIG. 1K illustrates the practically spherical shape of the combustion front of a traveling wave of nuclear fission, FIG. 18 illustrates a continuously curved surface of a combustion front of a traveling wave of nuclear fission, FIG. 1T illustrates the practically axisymmetric shape of the combustion front of a traveling wave of nuclear fission, FIG. Sh-1U illustrate practically η-fold axial symmetry of the shape of the combustion front of the traveling wave of nuclear fission, FIG. 1 \ U illustrates the asymmetric shape of the combustion front of a traveling wave of nuclear fission, FIG. 1X-1AP are block diagrams of parts of parts of the method of FIG. 1A, FIG. 2A is a flowchart of an illustrative method for controlling a traveling wave nuclear reactor; FIG. 2B-2M are block diagrams of parts of parts of the method of FIG. 2A, FIG. ZA is a block diagram of an illustrative system for a system for determining the movement of fuel fission subassemblies of nuclear fission, FIG. ZV-ZS are block diagrams of the components of the system of FIG. FOR, FIG. 4A is a block diagram of an illustrative system for moving fuel sub-assemblies of nuclear fission, FIG. 4B-4C are block diagrams of parts of system components in FIG. 4A, FIG. 5 is a block diagram in partial schematic view of an illustrative traveling wave nuclear reactor; FIG. 6A is a flowchart of an illustrative method of operating a traveling wave nuclear reactor; FIG. 6B is a flow chart of a detail of a part of the method of FIG. 6A, FIG. 7 is a flowchart of an illustrative method of operating a traveling wave nuclear reactor; FIG. 8 is a flowchart of an illustrative method of operating a traveling wave nuclear reactor; FIG. 9 is a flowchart of an illustrative method for operating a traveling wave nuclear reactor; FIG. 10A is a flowchart of an illustrative method of operating a nuclear reactor; FIG. 10B-NGOs are block diagrams of parts of parts of the method of FIG. 10A.

Detailed description

In the following detailed description, reference is made to the accompanying drawings. In these drawings, unless the context dictates otherwise, similar components are denoted by like numbers. The illustrative embodiments described in the detailed description, drawings, and claims are not to be construed as limiting the scope of the present invention. Other embodiments may be used and other changes may be made within the scope or scope of the subject matter presented in this application.

In accordance with illustrative embodiments, methods and systems for moving fuel assemblies in a nuclear fission reactor, methods for operating a traveling wave nuclear reactor, methods for controlling a traveling wave nuclear reactor, systems for controlling a traveling wave nuclear reactor, computer software products for controlling nuclear traveling wave reactor and traveling wave nuclear reactors with systems for moving fuel assemblies.

Overview of the traveling wave of nuclear fission.

Before details will be explained regarding non-limiting embodiments, a brief overview will be given regarding a traveling nuclear fission wave. Although a traveling nuclear fission wave is also known as a deflagration nuclear fission wave, for clarity, the term nuclear fission traveling wave will be used in the present description. Parts of the subsequent review include information taken from a report entitled Sotr1e1e1u Li1ota1eb No. 1c1eag Ro \\ e Keas1og8 Roth bopd-Tegt Oretabop: III. EiaShd Tesipo1uu Rot Yatde-8sa1e, botu-VBK. Ayotbaye Schleag E1esbtsyyu, authors Eb \\ agb Te11eg, Mshte1 [Mpkahua, Loteb \ Woo. Robeps Nube and 1oyp Yiskobk presented at a seminar in July 2003 at the Aspen Institute for Global Change, publication of the Livermore National Laboratory named after Lawrence (University of California) υθΚΕ-ΙΚ.ΝΡ-122708 (2003) (this report was prepared as an article for the journal Epegdu, 1p1etpaboeia1oitia1, November 30, 2003), the contents of which are hereby incorporated by reference.

In a wave that travels through the active zone of a nuclear reactor on a traveling wave with velocities of the order of about a centimeter per year, the reproduction material of nuclear fuel is reproduced into fissile material of nuclear fuel, which then undergoes fission.

Some of the nuclear fuels intended for use in traveling wave nuclear reactors are generally widely available, such as (without limitation) uranium (natural, depleted or enriched), thorium, plutonium, or even previously burned fuel assemblies. Other less widely available nuclear fuels can be used, such as (without limitation) other actinide elements or their isotopes. Some traveling-wave nuclear reactors require long-term operation with full power for about 30-50 years or longer. Some traveling-wave nuclear reactors do not require refueling with nuclear fuel (instead, they assume a landfill at the end of their service life), and some other traveling-wave nuclear reactors involve refueling with nuclear fuel, with some refueling with nuclear fuel at a scheduled shutdown, and some refueling nuclear fuel occur when working with energy generation. It is also assumed that in some cases, the regeneration of nuclear fuel can be avoided, thereby reducing the likelihood of military use and other problems.

The simultaneous fulfillment of desires to achieve exploitation of 30-50 years (or longer) at full capacity without refueling with nuclear fuel and to avoid nuclear fuel regeneration may entail the use of a spectrum of fast neutrons. In addition, the propagation of a traveling nuclear fission wave provides a high average burnup of unenriched actinide fuels, such as natural uranium or thorium, and the use of a relatively small region of the nuclear fission igniter of moderate isotopic enrichment of nuclear fissile materials in the fuel charge of the reactor core.

As such, a traveling wave nuclear reactor core may include a nuclear fission igniter and a larger propagation region of a deflagration nuclear fission combustion wave. The propagation region of a deflagration nuclear fission combustion wave contains thorium or uranium fuel and operates according to the general principle of nuclear fuel production using the fast neutron spectrum.

The active zone of a traveling wave nuclear reactor is a breeder reactor for reasons of efficient use of nuclear fuel and minimization of the need for isotope enrichment. In addition, the fast neutron spectrum is used because the large absorption cross section for fission products for thermal neutrons usually does not allow high utilization of thorium or the more abundant ²³⁸ υ uranium isotope in embodiments with uranium fuel without removing fission products.

An illustrative traveling wave of nuclear fission will now be explained. Propagation of deflagration combustion waves through nuclear fuel materials can release energy at predicted levels. In addition, if the material configuration has sufficiently time-independent features, for example, as the configurations found in typical industrial nuclear power reactors, then the subsequent energy production can be at a stable level. Finally, if the speed of propagation of a traveling wave could be controlled from the outside in a practically justified way, then the speed of release of energy and, thus, energy production could be controlled as required.

The following explains the nucleonics of a traveling wave of nuclear fission. The induction of nuclear fission of 3,204,235 selected isotopes of actinide elements, which are shared by the absorption of neutrons of any energy, can provide release of the binding energy of the nucleus at any temperature of the material, including arbitrarily low ones. Neutrons that are absorbed by a fissile actinide element can be created by a nuclear fission igniter.

The release of more than one neutron per absorbed neutron, on average, by nuclear fission of virtually any fissile actinide isotope can make it possible to diverge a neutron-mediated nuclear chain reaction. Typically, the number of neutrons released during each absorption is defined as η, where η = υσ (/ (σ (+ σ ₀ ), where σ is the number of neutrons released during fission. The release of more than two neutrons per absorbed neutron (in certain energy ranges neutrons, on average) can first allow the conversion of an atom of a non-fissile isotope into a fissile (via neutron capture and subsequent β-decay) by initial neutron capture, and then further allow the neutron to divide the nucleus of the newly created fissile isotope during the second glossing nuclear fission.

Many nuclear species with a high Ζ (Ζ> 90) can be used as nuclear fuel material in a traveling wave reactor (or breeder reactor) if, on average, one neutron from a given nuclear fission event can be radioactively captured in a non-fissionable but reproducing nucleus which then turns (for example, by β decay) into a fissile nucleus, and the second neutron from the same nuclear fission event can be captured on the fissile nucleus and, thereby, cause fission. In particular, if any of these conditions is established, the conditions for the propagation of a traveling wave of nuclear fission may be sufficient in this material.

Due to the β decay of the intermediate isotopes in the process of converting the reproducing nucleus to fissile, the rate at which fissile material is made available for fission is limited. Consequently, the characteristic wave propagation velocity is limited by half-lives of the order of several days or months. For example, the characteristic velocity can be of the order of the ratio of the distance traveled by a neutron from its birth during fission to its radiation capture on the reproducing nucleus (i.e., the mean free path) to the half-period (the longest-lived nucleus in the chain) of β decay resulting from the reproducing nucleus to fissile. For most cases of interest, this characteristic distance of neutron transport during fission in actinides of normal density is approximately 10 cm, and the half-period of β decay is 10 ⁵ -10 ⁶ s. Accordingly, for some designs, the characteristic wave velocity is 10 ^-4 -10 ^-7 cm / s. Moving at this relatively low speed indicates that the wave can be characterized as a traveling or deflagration wave, but not a detonation wave.

If a traveling wave tries to accelerate its advancement, its leading edge collides with an increasingly pure reproduction material (which is relatively neutron-loss material), since the concentration of fissile nuclei far in front of the center of the wave becomes exponentially low. Thus, the leading edge of the wave (referred to in this description as the combustion front) stops or slows down the propagation. Conversely, if a wave slows down propagation and the conversion coefficient is maintained above unity (i.e., the reproduction rate is higher than the fission rate), the local concentration of fissile nuclei from the ongoing β decay increases, local fission and neutron production rates increase and the leading edge of the wave, i.e. combustion front, accelerates.

Finally, if the heat associated with nuclear fission is quickly removed, all parts of the configuration of the initially reproducing substance in which the wave propagates are removed, propagation can occur at an arbitrarily low temperature of the material, although the temperatures of both neutrons and fissioning nuclei can be about 1 MeV.

These conditions for the initiation and propagation of a traveling wave of nuclear fission can be achieved with readily available materials. Although fissile isotopes of actinide elements are rarely found in the earth's crust both in absolute terms and in terms of reproducing isotopes of these elements, fissile isotopes can be concentrated, enriched and synthesized. For example, it is well known to use both natural and artificial fissile isotopes, such as and, and ⁹ Pu, respectively, for initiating nuclear chain reactions.

An examination of the corresponding neutron cross section suggests that a traveling nuclear fission wave can burn most of the core from natural actinides, such as ²³² Th or ^238, and if the neutron spectrum in the wave is hard or fast. That is, if neutrons that carry a chain reaction in a wave have energies that are not very small compared to about 1 MeV, at which they evaporate from early fission fragments, relatively large losses in the spatiotemporal local neutron balance can be avoided if the local the mass fraction of fission products becomes comparable with the mass fraction of reproducing material (remembering that 1 mol of fissile material during fission turns into 2 mol of fission product nuclei). At neutron energies <0.1 MeV, neutron losses can become significant even in typical structural materials of neutron reactors, such as Ta, which has the required properties at high temperatures.

Another consideration is the (relatively small) change in the incident neutron energy of the multiplicity of neutrons emitted during fission, ν, and the fraction of all neutron absorption events that lead to fission (and not just emission of γ-rays upon neutron capture), α. The algebraic sign of the function α (ν-2) constitutes the condition for the propagation of a traveling nuclear fission wave in a reproducing material compared to the overall balance of the fissile isotope mass in the absence of neutron leakage from the core or spurious absorption (such as fission products) in it, for each of the fissile isotopes of the reactor core. The algebraic sign is usually positive for all fissile isotopes of interest from neutron energies by fission of approximately 1 MeV down to the region of resonance capture.

The quantity α (ν-2) / ν determines the upper limit of the fraction of all neutrons produced by fission, which can be lost due to leakage, spurious absorption, or geometric divergence during the propagation of a traveling wave. It should be noted that this fraction is 0.15-0.30 for the main fissile isotopes in the neutron energy range, which prevails in all configurations of effectively immediate actinide isotopes of practical interest (approximately 0.1-1.5 MeV). In contrast to the situation prevailing for neutrons (above) thermal energy, in which spurious losses due to fission products dominate spurious losses during conversion from a reproducing element to fissile by 1-1.5 decimal orders of magnitude, the generation of fissile elements during capture by reproducing isotopes surpasses the capture of fission products by 0.7-1.5 orders of magnitude in the neutron energy range 0.1-1.5 MeV. The first assumes that the conversion from a reproducing element to a fissile one will be feasible only to the extent of 1.5-5% at or near the thermal energies of neutrons, while the latter indicates that transformations of more than 50% can be expected for the direct neutron neutron energy spectrum.

When considering the conditions for the propagation of a traveling nuclear fission wave for some approaches, neutron leakage for very large self-reflected actinide configurations can be effectively neglected. It is clear that the propagation of a traveling wave can be established in sufficiently large configurations of two types of actinides, which are relatively numerous in the earth's crust: Τΐι and and, the exceptional and main (i.e., the most long-lived) isotopic components of natural thorium and uranium, respectively.

In particular, the fission neutron transport in these actinide isotopes is likely to lead either to capture of the reproducing isotope on the nucleus or to fission of the fissioning nucleus before the neutron energy decreases significantly below 0.1 MeV (and after which it becomes amenable to non-negligible low probability of capture of the fission product at the core). It is clear that the concentration of fission product nuclei can approach or exceed the concentrations of reproducing nuclei in some cases, and the concentrations of fissile nuclei can be an order of magnitude lower than those of fission products or reproducing nuclei, while remaining quantitatively practically reliable. An examination of the corresponding neutron scattering cross sections suggests that the configurations of actinides that are extensive enough to be effectively infinitely thick, i.e. self-reflecting, for fission neutrons in their radial size, they will have density products with a radius of >> 200 g / cm ^- , i.e. they will have radii >> 10-20 cm of the density of the solid And- Τΐι.

A self-regulating wave (wave-samoyed) provides enough excess neutrons for the reproduction of a new fissile material of 1-2 medium free paths into an unburned fuel, effectively replacing the fissile fuel burned in the wave. The ash behind the peak of the combustion wave is practically neutron-neutral, since the neutron reactivity of its fissile fraction is balanced by parasitic absorption of structure reserves and fission products at the top of the leak. If the stock of fissile atoms in the center of the wave and immediately in front of it does not change with time as the wave propagates, then this happens stably; if it’s less, then the wave dies, and if it’s more, they can say that it is accelerating.

Thus, a traveling wave of nuclear fission can propagate and be maintained practically in steady state for a long time in the configurations of isotopes of natural actinides.

In the above description, using a non-limiting example of the present invention, round cylinders of natural uranium or thorium metal with a diameter of less than about 1 m (which can be significantly smaller in diameter when using effective neutron reflectors) that can stably propagate traveling nuclear waves divisions by arbitrarily large axial distances. However, the propagation of traveling nuclear fission waves should not be construed as being limited to circular cylinders, symmetric geometries or simply connected geometries. In this regard, additional embodiments of alternative geometries of the traveling wave nuclear reactor core are described in US Patent Application No. 11/605943 entitled ΑυΑ M'STN.LK ΡΟΑΤΗ KEASTOCK ROCK ΌΟΝΟΤΕΚΜ ΌΟΝΟΤΕΚΜ, in which KOOEK1SK Α. ΗΥΌΕ, MIKTEY Υ. Ι8ΗΙΚΑ \ Α, ΝΑΤΗΑΝ Ρ. ΜΥΗΚ- 5 024235

WOBE. ΑΝΏ b ^ b b. \ UOOE. 6K. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference.

Propagation of a traveling wave of nuclear fission has implications for embodiments of traveling wave nuclear reactors. As a first example, the rate of a local nuclear reaction can be superimposed with reasonable costs on the local temperature of the material in the neutron balance of a traveling wave. This large negative temperature coefficient of neutron reactivity makes it possible to control the speed of propagation of a traveling wave. If only very small thermal energy is extracted from the burning fuel, its temperature rises, and the temperature-dependent reactivity decreases, the nuclear fission rate in the center of the wave becomes correspondingly low, and the wave time equation reflects only a very low axial speed of advancement. Similarly, if the rate of extraction of thermal energy is high, the temperature of the material decreases and the neutron reactivity rises, the intra-wave balance of neutrons becomes relatively undamped and the wave travels in the axial direction relatively quickly. Details regarding illustrative temperature feedback implementations that may be included in reactor core assembly embodiments are described in US Patent Application No. 11/605933 under the name SOOTBOEE EO \ C. TERM ΘΡΈΚΑΤΊΘΝ OR Α HESELEK REASTOK, in which ROEER1SK Α. ΗΥΏΈ, MiK1EЬ. ΙδΗΙΚΑ \ Α, ΝΑΤΗΑΝ Ρ. MUNKOEE ΑΝΏ EOAE.E b. \\ 'OOE 1K. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference.

As a second example of the consequences of the propagation of a traveling wave of nuclear fission for embodiments of nuclear traveling wave reactors, less than all neutron production in fission in a traveling wave nuclear reactor can be used. For example, reactivity control systems, such as (without limitation) neutron-absorbing material in control rods or local modules that thermostat the material temperature, can use about 5-10% of the total neutron production in fission in a nuclear reactor 10 on a traveling wave. Another <10% of the total neutron production during fission in a traveling wave nuclear reactor can be lost to parasitic absorption in highly efficient heat-resistant structural materials (such as Ta, \ or Ke) used in the structural elements of a traveling wave nuclear reactor. This loss occurs in order to realize the required thermodynamic efficiency when converting to electrical energy and to achieve high system security. Ζ of these materials, such as Ta, \ and Ke, are approximately 80% of Ζ actinides, and thus their cross sections for radiation capture for high energy neutrons are not particularly small compared to their cross sections for radiation capture of actinides. The last 5-10% of the total neutron production during fission in a traveling wave nuclear reactor may be lost to spurious absorption in fission products. However, one can expect that the spectrum can be similar to the spectrum of a fast-neutron reactor cooled with liquid sodium in that parasitic absorption can account for only about 1-2% of the losses. As already noted, the neutron balance is characteristically rich enough that approximately 70% of the total neutron production during fission is sufficient to maintain the propagation of a traveling wave in the absence of leakage and rapid geometric divergence.

As a third example of the consequences of the propagation of a traveling wave of nuclear fission for embodiments of nuclear traveling wave reactors, high burnups (of the order of about 20-30%, or in some cases from about 40 or 50% to about 80%) of the initial stocks of actinide fuel characteristic of traveling waves nuclear fission, can provide highly efficient use of non-enriched fuel, in addition, without the need for regeneration.

It should be noted that the neutron flux from the most intensely burning region behind the combustion front reproduces the region rich in fissile isotopes at the leading edge of the combustion front, thereby serving to advance the traveling wave of nuclear fission. After the combustion front of the traveling wave of nuclear fission passes over a given mass of fuel, the concentration of fissile atoms continues to increase, while the radiative capture of neutrons in existing reproducing nuclei is much more likely than on the nuclei of fission products, while continued fission creates an increasing mass of fission products . The density of nuclear energy production in this area of fuel charge at any given time is maximum.

It is clear that far behind the advancing combustion front of a traveling wave of nuclear fission, the ratio of the concentration of fission product nuclei (the mass of which on average is almost exactly equal to half the mass of the fissile nucleus) and fissile nuclei increases to a value comparable to the ratio of active fission to radiation capture cross sections for fission products. In this case, the local neutron reactivity approaches a negative value or (in some embodiments) may become negative. Consequently, combustion and reproduction effectively stop. It is also understood that in some embodiments, non-fissile neutron-absorbing material, such as boron carbide, hafnium or gadolinium, may be added to ensure that local neutron reactivity is negative.

In some embodiments, the implementation of nuclear traveling wave reactors is all nuclear fuel,

- 6,024,235 ever used in a reactor is installed in the manufacture of a core assembly of a reactor. In addition, in some designs, spent fuel is never removed from the reactor core assembly. In one approach, these options for implementation can ensure operation without access to the reactor core after the start of nuclear fission, possibly after completion of the propagation of the combustion front.

In some other traveling wave nuclear reactor embodiments, all nuclear fuel ever used in a reactor is installed in a reactor core assembly, and in some designs, spent fuel is never removed from the reactor core assembly. However, and as will be explained below, at least some of the nuclear fuel can be moved or pulled between or among different places in the reactor core. This movement or dragging of at least a portion of the nuclear fuel may be performed to achieve the goals, as described below.

However, in some other traveling wave nuclear reactor embodiments, additional nuclear fuel may be added to the reactor core assembly after the start of nuclear fission. In some other traveling wave nuclear reactor embodiments, spent fuel may be removed from the reactor core assembly (and in some embodiments, spent fuel removal from the reactor core assembly may be performed when the traveling wave nuclear reactor is in power generation mode). This illustrative nuclear fueling and removal of spent fuel is explained in US Patent Application No. 11/605848, entitled ΜΕΤΗΟΏ ΑΝΏ δΥδΤΕΜ ROCK ΡΚΟνΡΚΟ РиЕЬ ΙΝ Α ХЕС1ТАК ΚΕΑΟΤΟΚ, in which ΚΟΏΕΚΙΟΚ Α. ΗΥΏΕ, ΜΕΚΙΡΙ, Υ. ΙδΗΙΚΑΑΑ. ΝΑΤΗΑΝ Ρ. ΜΥΗΚνΟΕΏ ΑΝΏ b 0 ^ b b. \ ΟΟΏ, 1K. named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference. Regardless of whether the spent fuel is removed or not, the preliminary expansion of the loaded fuel allows the replacement of higher density actinides with lower density fission products without any general volumetric changes in the fuel cells as the traveling nuclear fission wave travels along any given axial element of actinide fuel, turning it into ash - a fission product.

232,238

In general terms, the triggering of nuclear fission traveling waves in fuel loads from Tb or can be initiated by nuclear fission igniter modules, such as, without limitation, fuel assemblies enriched in fissile isotopes. Illustrative nuclear fission igniter modules and methods for launching traveling nuclear fission waves are described in detail in the co-pending application for US patent No. 12/069908 called ΝυΟΕΕΑΚ ΡΙ88ΙΟΝ ΙΟΝΙΤΕΚ, in which ΟΗΑΚΕΕδ Ε. ΑΗΕΡΕΕΏ, 1ΟΗΝ ΚΟΟΕΚδ ΟΙΕΕΕΕΑΝΏ, ΚΟΏΕΚΙΟΚ Α. ΗΥΏΕ, ΜΏΚΙΕΕ Υ. ΙδΗΙΚΑ \ Α, ΏΑνΙΏ Ο. ΜΟΑΏΕΕδ, ΝΑΤΗΑΝ Ρ. ΜΥΗΚνΟΕΏ, ΟΗΑΚΕΕδ \ ΗΙΤΜΕΚ ΑΝΏ Ι.ΟΑΕΙ.Ι. Ώ. \\ ΌΟΙλ J. are named as inventors, filed February 12, 2008, the contents of which are hereby incorporated by reference. Higher enrichments can result in more compact modules, and minimum mass modules can use moderator concentration gradients. In addition, the design of the nuclear fission igniter module may be determined in part by non-technical considerations, such as resistance to military use of materials in various scenarios.

In other approaches, illustrative nuclear fission ignitors may have other types of reactivity sources. For example, other nuclear fission igniters may include burning coals, such as nuclear fuel enriched in fissile isotopes when neutrons act in a traveling wave nuclear reactor. These burning coals can act as nuclear fission ignitors, despite the presence of various amounts of fission products (ash). In other approaches for launching a traveling nuclear fission wave, the nuclear fission igniter modules enriched in fissile isotopes can be used to supplement other neutron sources that use electrically driven sources of high energy ions (such as protons, deuterons, α particles, etc. .) or electrons, which in turn can produce neutrons. In one illustrative approach, a particle accelerator, such as a linear accelerator, can be located to feed high-energy protons into an intermediate material that, in turn, can produce these neutrons (for example, by fission). In another illustrative approach, a particle accelerator, such as a linear accelerator, can be located to feed high-energy electrons into the intermediate material, which, in turn, can produce these neutrons (for example, by electrodividing and (or) photo-dividing elements with high Ζ). Alternatively, neutrons can be produced by other known processes and devices emitting neutrons, such as in approaches with electrically induced fission (for example, 14 MeV neutrons from deuterium-tritium synthesis), and can be used in addition to nuclear fission igniter modules enriched in fissile isotopes to initiate the propagation of a fission wave.

Now, after considering the nucleonics of the fuel charge and the traveling wave of nuclear fission, further details will be considered regarding the ignition of the fission reaction and the maintenance of the traveling wave of nuclear fission. A centrally located illustrative nuclear fission igniter moderately enriched in fissile material, such as or ⁹ Pu, has neutron-absorbing material (such as borohybrid or the like) removed from it (for example, by electrical heating on the operator’s command or by extraction of one or more control rods), and the nuclear fission igniter becomes neutron critical. The local temperature of the fuel rises to a predetermined temperature, and then is regulated, for example, by the reactor coolant system and (or) the reactivity control system or local thermostatic modules (which is described in detail in US patent application No. 11/605943 under the name ΛυΤΘΜΆΤΕΌ ХИСЬЕАК RO \\ ТК КЕАСТОК ROCK ROHS-TRKM ΟΡΕΚΑΤΙΟΝ, in which KONRK1SK A. ΗΥΏΕ, MiK1Eb Υ. ΙδΗΙΚΑ \ Α, ΝΑΤΗΑΝ Ρ. ΜΥΗΚVΟ ^^, ΑΝΏ EO \ REE.. \ OOE, 1K. Are named as inventors, filed November 28, 2006, contents which reference is included in the present description). The neutrons from fission under the action of fast neutrons υ or Ри are captured, mainly, first at the local υ or Τΐι.

It is clear that the enrichment of uranium of a nuclear fission igniter can be reduced to levels not much higher than in the case of fuel for a light-water nuclear reactor (L \ K) by introducing nuclear fission into the igniter and the fuel region directly surrounding it with a radial density gradient of the refractory moderator, such as graphite. The high density of the moderator allows poorly enriched fuel to satisfactorily burn out, and a decrease in the density of the moderator ensures the efficient reproduction of fissile material. Thus, an optimal nuclear fission igniter design may include a trade-off between propagation stability and minimum latency from initial criticality to full rated power from a fully ignited core fuel load. The lower enrichment of the nuclear fission igniter will entail more reproducing generations and thus impose longer latencies.

In some embodiments, the peak reactivity of the reactor core assembly in the first stage of the firing reaction of the fission reaction may slowly decrease, because although the total number of fissile isotopes increases, this total number becomes more spatially dispersed. As a result of choosing the initial geometry of the fuel, enriching the fuel depending on the position and density of the fuel, it can be positioned for maximum reactivity, but in order to still be slightly positive at the point in time at which its minimum value is reached. Soon after, the maximum reactivity begins to increase rapidly to its largest value, corresponding to the total number of fissile isotopes in the reproduction area, significantly exceeding their total number remaining in the nuclear fission igniter. For many cases, the quasispherical annular shell then provides maximum specific energy production. At this point in time, the fuel load of the reactor core assembly may be referred to as ignited.

Now we will consider the propagation of a traveling wave of nuclear fission, which in the text of the present description may also be referred to as the burning of nuclear fuel. In the previously described embodiment, a spherically diverging shell with a maximum specific nuclear energy production continues to move radially from the nuclear fission igniter to the outer surface of the fuel charge. Reaching the outer surface, it is usually divided into two spherical zonal surfaces, with each surface extending in the corresponding one of two opposite directions along the axis of the cylinder. At this point in time, the full potential of heat production can develop. This interval is characterized as such by the period of the start of the combustion fronts of two traveling propagating waves of nuclear fission propagating in the axial direction. In some embodiments, the core of the core fuel is ignited, and two waves are generated, propagating in opposite directions. This design doubles the mass and volume of the core in which energy production occurs at any given moment, and thus halves the peak specific energy production of the core, thereby minimizing quantitatively the transfer problems for thermal neutrons. However, in other embodiments, the core fuel loading is ignited at or near one end, as required for a particular application. Such an approach can result in a single propagating wave in some designs.

In other embodiments, the core fuel loading may be ignited in several places. In yet other embodiments, the core fuel loading is ignited at any three-dimensional location in the core, as required for a particular application. In some embodiments, two propagating traveling nuclear fission waves may be initiated and propagated away from the site of firing the fission reaction; however, depending on the geometry, composition of the nuclear fuel, or for other reasons, the action of the neutron-modifying control structure, different quantities (for example, one, three or more) of traveling fission waves can be initiated and propagated. However, for understanding and brevity, consideration in the text of the present description refers (without limitation) to the propagation of the combustion fronts of two traveling nuclear fission waves.

- 8 024235

From this moment onwards, by breaking up two waves, when they reach two opposite ends or approach them, the physics of nuclear energy production is usually effectively constant in time within any wave. The speed of wave propagation through the fuel is proportional to the local neutron flux, which, in turn, is linearly dependent on the thermal energy extracted from the assembly of the reactor core by the combined action of the traveling wave of the neutron control system on the neutron balance. In one approach, a neutron control system may be implemented with thermostatic modules (not shown), as described in US Patent Application No. 11/605933, entitled SOETKLBYE OYS TEKM ΟΡΕΚΑΤΙΟΝ OR A NYSELK Keastok, in which KO1) ЕК1СК Α. ΗΥΏΈ, MIMEЬ Υ. ΙδΙΙΙΚΑΥΑ. ΝΑΤΗΑΝ Ρ. \ 1ΥΙΙΚ \ ΌΕΙ) ΑΝΩ b 0 ^ b b. HOOOOE. G. are named as inventors, filed November 28, 2006, the contents of which are hereby incorporated by reference. In other approaches, the neutron control system can be implemented with one or more rods containing neutron-absorbing material and moved by one or more drive mechanisms of the control rods.

If a higher power is required from the reactor by means of a low-temperature coolant flowing into the core, in some embodiments, the temperature of the two ends of the core (which, in some embodiments, are closest to the coolant inlet openings) decreases slightly below the design setting of thermostatic modules, while the neutron absorber is pulled from the corresponding sub-population of thermostatic core modules, and the local neutron flux is allowed When this increase to bring the local thermal power production to the level which drives the local material temperature setpoint to the local thermostating modules. In some other embodiments, temperature control may be performed by shimming control rods, as required in response to changes in controlled temperature.

However, in the embodiment with two combustion fronts, this process is ineffective in terms of significant heating of the coolant, while its two separated streams move into two nuclear combustion fronts. These two parts of the core fuel load, which can produce significant levels of atomic energy if not suppressed by neutron absorbers, then act to heat the coolant to the temperature indicated by the design setting of their modules, provided that the temperature of the nuclear fuel does not become excessive (and regardless of temperature at which the coolant has arrived in the core). Then, two coolant flows move through two sections of already burnt fuel to the center of two combustion fronts, removing residual nuclear fission from them and removing residual heat in the existing fuel load in its middle. This design facilitates the propagation of two combustion fronts towards the two ends of the fuel charge by trimming the excess neutrons, mainly from the trailing edge of each front.

Thus, core neutronics in this design can be considered practically self-regulating. For example, for embodiments with a cylindrical core, the core nucleonics can be considered almost self-regulating if the product of the fuel density and the radius of the cylindrical core is> 200 g / cm ² (i.e., 1-2 average free paths for neutron-induced fission in the core typical composition for a moderately fast neutron spectrum). One function of a neutron reflector in such a core design may be to significantly reduce the integral fast neutron flux density (fluence) observed in the outer parts of the reactor, such as its radiation shield, structural supports, outer shell and components of the reactivity control system, such as (without limitation) control rods (if provided) or thermostatic modules (if provided). In addition, the neutron reflector can affect the core by increasing the efficiency of reproduction and specific energy in the outer parts of the fuel. This effect can increase reactor profitability. The peripheral parts of the fuel charge are not used at low overall energy efficiency, but they have isotope burnout levels comparable to burnout levels in the middle of the fuel load.

Although core neutronics in this design can be considered practically self-regulating, other designs can operate under the control of a reactor control system that contains a corresponding electronic controller having a corresponding electrical circuit and which may contain a corresponding electromechanical system, such as one or more rods, neutron-absorbing material and moved by one or more drive mechanisms of the control rods her.

Finally, irreversible reduction of the reactivity of neutrons in the core can be carried out at any time by introducing a neutron absorber into the coolant flow, as required. For example, a light load of the coolant flow with a material such as BP ₃ , possibly simultaneously with a volatile reducing agent, such as Η2, if necessary, can lead to the deposition of metal boron almost uniformly on the inner walls of the coolant pipes passing through the reactor core, due to for exponential acceleration of an otherwise slow chemical reaction

- 9 024235

2BP ₃ + 3H ₂ ^ 2B + 6HP with high temperatures arising in it. Boron, in turn, is a highly refractory metalloid and will usually not migrate from its deposition site. The almost uniform presence of boron in the core in quantities <100 kg can negate the reactivity of the neutrons in the core for an indefinitely long time without involving the use of drive mechanisms near the reactor.

In a general sense, specialists will understand that the various aspects described in this document, which can be implemented separately and (or) together, with a variety of hardware, types of software, software and hardware and / or any combination of them, can be considered as consisting of various types of electrical circuits. Therefore, as used in the present description, the term electrical circuits includes, without limitation, electrical circuits having at least one discrete electrical circuit, electrical circuits having at least one integrated circuit, electrical circuits having at least one specialized integrated circuit, electrical circuits forming a universal computing device configured by a computer program (eg, a universal computer, configured a computer program that at least partially implements the processes and / or devices described herein, or a microprocessor configured by a computer program that at least partially implements the processes and / or devices described herein ), electrical circuits forming a storage device (for example, types of memory (for example, RAM, flash memory, read only memory, etc.)), and (or) electrical circuits forming a communication device (for example p modem connected switch (switch), the opto-electric equipment, etc.). Those skilled in the art will understand that the subject matter described herein may be implemented in analog or digital form or in some combination thereof.

In a general sense, those skilled in the art will understand that the various aspects described herein that can be implemented separately and (or) together by different types of electromechanical systems having a wide variety of electrical components, such as hardware, software, and hardware and software and (or) their almost any combination; and a variety of components that can exert mechanical force or impart movement, such as rigid bodies, spring or torsion bodies, hydraulic devices, devices with an electromagnetic drive and (or) almost any combination of them. Therefore, in the sense in which it is used in the present description, the term electromechanical system includes, without limitation, electrical circuits functionally connected to the transducer (e.g., actuator, electric motor, piezoelectric crystal, microelectromechanical system (ΜΕΜδ), etc. ), electrical circuits having at least one discrete electrical circuit, electrical circuits having at least one integrated circuit, electrical circuits having at least one cn a personalized integrated circuit, electrical circuits forming a universal computing device configured by a computer program (for example, a universal computer configured by a computer program that at least partially implements the processes and / or devices described herein, or a microprocessor configured by a computer a program that at least partially implements the processes and (or) devices described herein), electrical circuits, arr indicating a storage device (for example, types of memory (for example, random access memory, flash memory, read-only memory, etc.)), electrical circuits forming a communication device (for example, modem, communication switch (switch), optoelectric equipment, etc. .d.) and (or) any non-electric analogue thereof, for example optical or other analogs. Those skilled in the art will also understand that examples of an electromechanical system include, but are not limited to, a wide variety of consumer electronics systems, medical devices, and other systems such as automobile transport systems, factory automation systems, security systems, and / or communications / computing systems. Those skilled in the art will understand that unless the context may dictate otherwise, the term electromechanical as used in the present description is not necessarily limited to a system having both an electric and a mechanical drive.

Illustrative Embodiments

Now, after a brief overview is given regarding the initiation and propagation of a traveling wave of nuclear fission, illustrative embodiments will be explained with examples not limiting the scope of the present invention.

The following is a series of flowcharts illustrating embodiments of the present invention. For ease of understanding, flowcharts are structured and presented in such a way that the initial flowcharts represent embodiments by means of an exemplary embodiment, and then the subsequent flowcharts represent alternative embodiments and / or extensions of the initial flowchart (flowcharts) or as subcomponent, or as an additional component in relation to one or more block diagrams presented on one or more of the previously mentioned

- 10,024,235 flowcharts. Those skilled in the art will understand that the presentation style used in the present description (for example, starting with presenting a flowchart (s) representing (representing) an exemplary (s) implementation (s), and then providing additions and (or) further details in the following flowcharts) typically provides a quick and easy understanding of the various process embodiments. In addition, specialists will understand that the presentation style used in the present description is still well suited to the paradigms of modular and (or) object-oriented programming.

Turning now to FIG. 1A, which, as a general view, shows an illustrative method 10 for operating a traveling wave nuclear reactor. Turning further to FIG. 1B, which, by way of example, not limiting the scope of the present invention, illustrates components of an illustrative traveling-wave nuclear reactor 12. In the assembly 16 of the reactor core are fuel subassemblies 14 nuclear fission. For clarity, FIG. 1B may illustrate less than all nuclear fission fuel subassemblies 14 that can be accommodated in reactor core assembly 16 embodiments.

In assembly 16 of the reactor core, a coordinate system is defined. In some embodiments, the coordinate system may be determined by an x-dimension, a y-dimension, and a ζ-dimension. In some other embodiments, the coordinate system may be determined by a radial dimension and an axial dimension. In some other embodiments, the coordinate system may include an axial dimension and a lateral dimension.

In some embodiments, the nuclear fission fuel assemblies 14 may be separate nuclear fuel elements such as rods, plates, spheres, and the like. nuclear fuel. In some other embodiments, the nuclear fission fuel assemblies 14 may be nuclear fission fuel assemblies, i.e. two or more individual nuclear fuel elements grouped into an assembly. Whatever the embodiment of the nuclear fission fuel assemblies 14, the nuclear fuel material contained in the nuclear fission fuel assemblies 14 may be any suitable type of nuclear fuel material, as described above.

As a general idea, the application of method 10 begins with block 18. In block 20, the front of burning of a traveling nuclear fission wave propagates (as shown by arrows 24) in the first and second dimensions in the fuel fission subassemblies 14 of the nuclear fission in the assembly 16 of the nuclear core 12 traveling wave reactor. In block 26, the selected nuclear fission fuel assemblies 14 are controllably moved in the first dimension from the respective first places to the corresponding second places so as to determine the shape of the burning front of the nuclear fission traveling wave 22 in the second dimension in accordance with the selected set of dimensional constraints. Method 10 is stopped at block 28.

Now, with examples not limiting the scope of the present invention, some illustrative details will be explained.

The fuel subassemblies 14 of nuclear fission carry a spatial relationship with the dimensions designated as the first and second dimensions. For example, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension. In some embodiments, the second dimension may be a y-dimension or an axial dimension. In some other embodiments, the second measurement may be an x-measurement, a ζ measurement, or a side measurement.

In addition, in some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

As the first dimension and the second dimension, different dimensions can be designated. For example, in some embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension. In some other embodiments, the first dimension may be an axial dimension, and the second dimension may be a radial dimension. In some embodiments, the first dimension may be an axial dimension, and the second dimension may be a lateral dimension. In some other embodiments, the first dimension may be a lateral dimension, and the second dimension may be an axial dimension. In a cylindrical core with axially elongated assemblies, such as in typical configurations of industrial light water nuclear reactors, the first measurement may be a radial measurement and the second measurement may be an axial measurement. In other reactor configurations, such as the configuration of heavy water reactors ί'ίυ. fuel assemblies are elongated in the first dimension and can be moved in a lateral or radial second dimension.

As shown in FIG. 1B, locations in the reactor core 12 according to various attributes may be characterized as first places and second places. Typically, a place can be considered as a space near the area of the active zone 12 of the reactor fuel subassembly 14 nuclear

- 11,024,235 divisions. In addition, the site can be considered in general as the space directly surrounding any given zone in the reactor core 12, or can be considered as a large part of the reactor core 12. For example, if we turn in addition to FIG. 1C, in some embodiments, the first locations may be outwardly directed locations 30, and the second locations may be inwardly oriented locations 32. As shown in FIG. 1C, in some embodiments, inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12. In some other embodiments, the implementation of inwardly directed places and outwardly directed places can be based on the neutron flux so that the neutron flux in the inwardly directed places is greater than the neutron flux in the outwardly directed places. In some other embodiments, inwardly directed and outwardly directed sites may be based on reactivity such that k _{e [1es1 |} , _e in inwardly directed places is higher than in the outwardly directed places. Embodiments typical of a traveling wave reactor may have outwardly directed places, including places outside or in the direction of the propagating wave, and inwardly directed places may include places through which the traveling nuclear fission wave propagates or has already spread.

Consider further examples if we turn in addition to FIG. 1Ό. In some embodiments, the first seats may include inwardly extending locations 32, and the second locations may include outwardly extending locations 30. As shown in FIG. 1Ό, in some embodiments, inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12. In some other embodiments, the implementation of inwardly directed places and outwardly directed places can be based on the neutron flux so that the neutron flux in the inwardly directed places is greater than the neutron flux in the outwardly directed places. In some other embodiments, the implementation of inwardly directed places and outwardly directed places may be based on reactivity such that k _{e [1c1 | ye} in inwardly directed places is higher than k _{[1c1 |} ,, _e in outward places. In other embodiments, inwardly directed and outwardly directed places can be described in terms of a predominant nuclear reaction occurring in these areas. As an example, not limiting the scope of the present invention, an inwardly directed site may be characterized by predominant nuclear fission reactions, while an outwardly directed site may be characterized by predominant nuclear absorption reactions on the reproducing material.

Regardless of the characterization of first places and second places, as well as inwardly directed places or outwardly directed places, first places and second places may be characterized according to these attributes. For example, in some embodiments, the first places and second places may be on opposite sides of the initial value in the first dimension. In some other embodiments, the first places and second places may include at least one attribute that is substantially equalized. For example, at least one attribute, which is practically equalized, may contain geometric proximity to the central region of the reactor core, neutron flux, reactivity, and the like.

As one non-limiting example, shown in FIG. 1E, the selected nuclear fission fuel subassemblies (not shown for clarity) can be controlled radially outward from the respective inwardly directed locations 32 to the corresponding outwardly directed locations 30 so as to determine the shape of the combustion front 22 of the traveling nuclear fission wave in the axial direction in accordance with the selected a set of dimensional restrictions. As an illustration and not as limiting the scope of the present invention, axial changes in the shape of the burning front of a nuclear fission traveling wave 22 during radial movement of nuclear fission fuel assemblies (not shown) are shown. The left drawing illustrates the initial shape of the combustion front 22 of a traveling wave of nuclear fission. It is clear that for the sake of clarity, only a quarter of the perimeter of the combustion front 22 of the traveling wave of nuclear fission is shown.

In the drawing in the center, the selected nuclear fission fuel assembly (not shown) was radially moved from the inwardly directed location 32 to the outwardly directed location 30 after the selected nuclear fission fuel assembly (not shown) burned for the required time or in accordance with the required reactivity parameter (such as, without limitation, burnout). The reactivity moved radially outward from the peak, which was radially located in the inwardly directed position 32 (as shown in the left drawing), to the outwardly directed place 30 (as shown in the drawing in the center).

Over the life of the active zone 12 of the traveling wave nuclear reactor, additional nuclear fission fuel assemblies (not shown) can radially rearrange outward from inwardly located locations 32 to outwardly directed locations 30. As a result of this additional outward directed movement, the nuclear fission fuel assemblies (not shown) in places radially directed inward in the active zone 12 of a nuclear reactor on a traveling wave they can be kept from burning more than fuel assemblies nuclear fission (not shown)

- 12,024,335 in radially outwardly directed places in the active zone 12 of a traveling wave nuclear reactor. As shown in the right drawing, if a sufficient number of nuclear fission fuel subassemblies are moved radially outward, as described above, then the shape of the burning front of the nuclear fission traveling wave 22 can approximate the Bessel function (cylindrical function). In addition, if a sufficient number of nuclear fission fuel subassemblies are moved radially outward, as described above, then all or almost all of the nuclear fission fuel subassemblies in the active zone 12 of a traveling wave nuclear reactor can reach their respective burnup limits or approach them almost simultaneously. In this case, the use of nuclear fission fuel subassemblies in the active zone 12 of the traveling wave nuclear reactor is maximized.

As another non-limiting example, shown in FIG. 1P, the selected nuclear fission fuel assemblies 14 can be controlled radially outward from the respective inwardly directed seats 32 toward the corresponding outwardly directed seats 30, and the other nuclear fission fuel assemblies 14 ′ can be controlled radially inwardly moved from the corresponding outwardly directed locations 30 toward the corresponding directed inward places 32 so as to determine the shape of the combustion front 22 of the traveling wave of nuclear fission in the axial direction in accordance with the selected set rum dimensional constraints. That is, the selected nuclear fission fuel assemblies 14 and 14 ′ are interchanged between the inwardly directed locations 32 and the outwardly directed locations 30.

As an illustration and not as a limitation of the scope of the present invention, axial changes in the shape of the burning front of a nuclear fission traveling wave 22 are shown with interchangeable radial movement of the nuclear fission fuel assemblies 14 and 14 '. The left drawing illustrates the initial shape of the combustion front 22 of a traveling wave of nuclear fission. In the left drawing, the nuclear fission fuel assemblies 14 have more fissile content than the nuclear fission fuel assemblies 14 ′. For example, nuclear fission fuel subassemblies 14 may be part of an igniter assembly for a traveling wave nuclear reactor 12. As another example, nuclear fission assemblies 14 may contain fissile material obtained from a reproducing isotopic material as a result of the absorption of fast neutrons in the active zone 12 of a traveling wave nuclear reactor and subsequent nuclear conversion into fissile isotopes. In contrast, the nuclear fission fuel subassemblies 14 ′ have less fissile content than the nuclear fission fuel assemblies 14. In some cases, the nuclear fission fuel subassemblies 14 ′ may contain more reproducing isotopic contents than the nuclear fission fuel subassemblies 14. In such cases, the nuclear fission fuel subassemblies 14 ′ are more absorbent for fast neutrons than the nuclear fission fuel subassemblies 14.

In the right drawing, the selected nuclear fission fuel subassembly 14 was moved radially outward from the inwardly directed space 32 to the outwardly directed place 30, and the selected nuclear fission fuel subassembly 14 'was moved radially inward from the outwardly directed place 30 to the inwardly directed location 32. After exchanging the places of the fuel subassembly 14 and 14 'nuclear fission, the axial profile of the front of combustion 22 of the traveling wave of nuclear fission made more compact and more uniform than the axial profile of the front of 22 mountains Nia traveling wave nuclear fission before swapping (see. the left drawing). As a result, in some embodiments, for a combustion front 22 of a traveling nuclear fission wave, a substantially uniform or uniform profile can be achieved. In some other embodiments, it may not be necessary to achieve a substantially uniform or uniform profile for the combustion front 22 of the traveling nuclear fission wave. In these cases, you may just need to move fissile material or move reproductive isotopic material. In some other embodiments, it may be necessary to expand the combustion front 22 of the traveling nuclear fission traveling wave in the radial dimension.

Turning further to FIG. 10. The shape of the burning front of the nuclear fission traveling wave can also be determined in the radial dimension by moving the fuel fission subassemblies 14 and 14 ′ in the radial dimension, as discussed above with reference to FIG. 1P. The radial profile of the combustion front 22 of the traveling wave of nuclear fission can be considered as representing the neutron leakage current. In the left and right drawings of FIG. 10 shows views along the axial dimension corresponding to the left and right drawings, respectively, of FIG. 1P.

Turning now to FIG. 1H. The selected nuclear fission fuel assemblies 14 can be controlled laterally from the respective first places towards the corresponding second places so as to determine the shape of the combustion front 22 of the traveling nuclear fission wave in the radial direction in accordance with the selected set of dimensional restrictions.

The left drawing illustrates the initial shape of the combustion front 22 of the traveling wave of nuclear fission, when viewed in axial dimension. The selected nuclear fission fuel assembly 14 is located in the first place ζ, g, φ ₁ . In this example, shown for illustrative purposes, the fuel fission subassembly 14 of nuclear fission 14 introduces reactivity in the first place ζ, g, φ _μ which can be determined (for any reason) in excess of the amount of reactivity required in the first place ζ, g, φ ! For example, a nuclear fission fuel assembly 14 may be part of an igniter assembly for a traveling wave nuclear reactor 12. As yet another example, a nuclear fission fuel assembly 14 may comprise fissile material obtained from a reproducing isotopic material as a result of the absorption of fast neutrons in the active zone 12 of a traveling wave nuclear reactor and subsequent nuclear conversion into fissile isotopes. As a result, the combustion front 22 of the traveling wave of nuclear fission can propagate too much in the radial direction in the first place ζ, g, φι.

As shown in the right drawing, the selected nuclear fission fuel assembly 14 was moved along the lateral measurement φ from the first location ζ, g, φι to the second location ζ, g, φ ₂ . It is clear that the shape of the combustion front 22 of the traveling nuclear fission wave is determined radially as a result of lateral displacement of the selected nuclear fission fuel assembly 14 from the first place ζ, g, φι to the second place ζ, g, φ ₂ . The lateral movement of the selected nuclear fission fuel subassembly from the first place ζ, g, φι to the second place ζ, g, φ ₂ removed the fissile content from the first place ζ, g, φι and added the fissile content to the second place ζ, g, φι. As shown in the right drawing, the shape of the combustion front 22 of the traveling nuclear fission wave shortened along the radial dimension r near the first place ζ, g, φι and lengthened along the radial dimension r near the second place ζ, g, φ ₂ .

The controlled movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 26 may entail one or more processes. For example, and if we turn in addition to FIG. 11 and 11, in some embodiments, the controllable movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second locations in block 26 may include rotating at least one of the selected nuclear fission fuel subassemblies 14 in block 34, as shown arrow 36 (Fig. 11). It is clear that the rotation of at least one of the selected nuclear fission fuel assemblies 14 in block 34 can be performed by any suitable fuel handling system located in the core as required. In addition, it may be necessary to rotate the selected nuclear fission fuel subassemblies 14 in order to minimize or prevent deformation of the reactor construction material, such as bending of the nuclear fission fuel subassemblies.

As another example, if we turn in addition to FIG. 1K and 1b, in some other embodiments, the controllable movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second locations in block 26 may include turning at least one of the selected nuclear fission fuel subassemblies 14 in block 38, as shown by arrows 40 (Fig. 1b). It is clear that the turning over of at least one of the selected nuclear fission fuel assemblies 14 in block 38 may be performed by any suitable fuel handling system located in the core as required. Turning over the nuclear fission subassembly 14 may cause the inlet of the nuclear fission subassembly 14 (before flipping) to become the release of the nuclear fission subassembling 14 (after flipping), and u1ce уег8а. This inversion can result in axial equalization of thermal stresses and (or) the effect of radiation on the nuclear fission fuel subassembly 14 at the ends of the nuclear fission fuel subassembly 14. Any of these radiation actions may be related to temperature and (or) may be associated with changes in the neutron flux at the axial ends of the reactor core 12. It is clear that the inversion of the nuclear fission subassembly 14 causes both ends of the inverted nuclear fission subassembly 14 to move from first place to second place relative to the central turning point. However, in some cases, it may be necessary to change the assembly location in the lateral direction.

It is also clear that one or more dimensional constraints can be selected as required for a particular application. For example, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension.

In some other embodiments, the selected set of dimensional constraints may be a function of at least one of the criteria of the combustion front. For example, a criterion for a combustion front may include a neutron flux. In some embodiments, a neutron flux may be associated with at least one of the selected nuclear fission fuel assemblies 14. In some other embodiments, the combustion front criterion may include neutron fluence. In some embodiments, the neutron fluence may be associated with at least one of the selected nuclear fission fuel assemblies 14.

In some other embodiments, combustion front criteria may include nuclear fuel burnup. In some embodiments, the burnup of nuclear fuel may be associated with at least one of the selected nuclear fission fuel assemblies 14. In such embodiments, it may be necessary to move the selected nuclear fission subassemblies 14 from a first location having a first burnout rate to a second location having a second burnout speed. If the selected nuclear fission subassembly 14 is nearing the end of its service life, then the first place may be a place characterized by a high burn-up rate, and the second place may be a place characterized by a lower burn-out speed (relatively high burn-up speed in the first place) or an almost zero value burnout rate. In embodiments in which the nuclear fission fuel assembly 14 is reproduced, it may be necessary to move the nuclear fission fuel assembly 14 from a first location having a low burnup rate to a second location having a higher burnup rate (relative to a burnout of the first place).

In some other embodiments, the implementation of the criteria of the combustion front may include the location of the combustion front within at least one of the selected nuclear fission subassemblies 14. The location of the combustion front can be characterized by signs of the active zone 12 of a traveling wave nuclear reactor or of fuel subassemblies 14 of nuclear fission in it. These features may include, among others, the rate of division, reproduction rate, output power, temperature, reactivity, etc., but not be limited by these parameters.

It is clear that the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places in block 26 can be performed in any way as required for a particular application. For example, if we turn in addition to FIG. 1M (and as shown in FIGS. 1C and 1Ό), in some embodiments, the controlled movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second locations in block 26 may include controlled radial movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 42. It is clear that the radial movement in block 42 can be performed by any suitable maneuver system ulirovaniya fuel located in the core, as required.

In some other embodiments, if we refer further to FIG. 1Ν and 1O, the controlled movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 26 may be the controlled spiral movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 44, as shown by arrow 46. It is clear that the spiral movement in block 44 can be performed by any suitable fuel handling system, finding in the core, as required.

In some other embodiments, if we refer further to FIG. 1P and 1C, the controlled movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 26 may be the controlled movement of the selected nuclear fission fuel assemblies 14 axially along the first measurement from the corresponding first places to the corresponding second places in block 48, as shown by arrow 50. It is clear that the axial movement in block 48 can be performed by any suitable fuel handling system, finding ysya in the core as required.

It is clear that the shape of the burning front of a nuclear fission traveling wave can be determined by any parameter related to the burning front of a nuclear fission traveling wave 22, such as an unlimited neutron flux, neutron fluence, burnup, and / or reactivity (or any of their components). It is also clear that the combustion front 22 of the traveling wave of nuclear fission can take any form that is required for a particular application. For example, if we turn in addition to FIG. 1K, in some embodiments, the shape of the combustion front 22 of a traveling nuclear fission wave may be substantially spherical. In some other embodiments, if we refer further to FIG. 18, the shape of the combustion front 22 of a traveling nuclear fission wave can practically correspond to a continuously selected curved surface. In some embodiments, if we refer further to FIG. 1T, the shape of the combustion front 22 of a traveling nuclear fission wave can be almost axisymmetric with respect to the second dimension. In some other embodiments, if we refer further to FIG. 1i and 1U, the shape of the combustion front 22 of the traveling wave of nuclear fission can have almost n-fold axial symmetry with respect to the second dimension.

It is known to those skilled in the art that maintaining a substantially constant, flat, combustion profile (such as the Bessel function) in the reactor core reduces the formation of sharp maxima among the nuclear fission fuel subassemblies in the core and increases fuel use. In the traveling wave nuclear reactor described above, the combustion region of the reactor typically expands in size due to the high reproduction rate. The burning area is supported by a sufficient supply of nuclear material, such as reproducing isotopic material

- 15,024,235 or fissile material to maintain a high reproduction rate.

It is clear that in some reactor designs there are advantages in moving the nuclear fission fuel subassemblies, as described above, in order to maintain the required characteristics of the combustion front. For example, moving the nuclear fission fuel subassemblies radially into the combustion region may act to supply either a reproducing isotopic material or fissile material to the reaction zone. The movement of the nuclear fission fuel subassemblies radially outward may serve to move the nuclear fission fuel subassemblies, having reached their burnup limit, from the zone of high neutron activity. Movement directed radially outward can also serve to reduce the energy density of the combustion region by spreading fissile, burnable, nuclear fuel material in areas that have not yet reacted. It is clear that radial movement in combination with spiral movement provides a slower spatial increment of radial movement with azimuthal movement for the further formation of the combustion front. It is also clear that in some cases the fuel subassemblies of nuclear fission can change places (or alternate) with other fuel subassemblies in other places. In these cases, reproducing isotopic material from the reproduction zone can be replaced by well-burnt material from the combustion zone of the reactor. In other cases, the nuclear fuel material may be replaced from places directly adjacent to the reactor core, for example, from two or more replaced places of the nuclear fission fuel subassemblies.

In some embodiments, if we refer further to FIG. 1 \ ν, the shape of the combustion front 22 of the traveling wave of nuclear fission along the second dimension can be asymmetric. In some embodiments, the shape of the burning front of the nuclear fission traveling wave may be axisymmetric (characterized by axial asymmetry) with respect to the second dimension.

In some embodiments, if we refer further to FIG. 1X, method 20 may also include a stage at which (at block 52) a combustion front of a traveling nuclear fission wave is ignited by igniter assemblies (not shown) of a nuclear fission traveling wave. Illustrative examples of the initiation of a traveling wave of nuclear fission by assemblies of the igniter of a traveling wave of nuclear fission are described above, and there is no need for repetition. Turning further to FIG. 1Υ. At block 54, at least one of the nuclear fission wave igniter wave assemblies may be removed before the controlled movement of selected nuclear fission fuel subassemblies along the first measurement from respective first places to corresponding second places. Turning further to FIG. 1Ζ. In some embodiments, the removal of at least one of the nuclear fission traveling wave igniter assemblies in block 54 before the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second places may include (in block 56) removing at least one from igniter assemblies of a traveling nuclear fission wave from second places before the controlled movement of selected nuclear fission fuel assemblies along the first dimension of respective first seats in a respective second location.

In some embodiments, if we refer further to FIG. 1AA, in block 58, it is caused that the traveling wave nuclear reactor becomes subcritical before the controlled movement of the selected nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places. For example, if we turn in addition to FIG. 1AB, in some embodiments, causing the traveling wave reactor to become subcritical (at block 58) may include introducing neutron-absorbing material into the reactor core at block 60.

Turning further to FIG. 1AC. In some embodiments, at block 62, criticality can be restored after a controlled movement of selected nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places. For example, if we turn in addition to FIG. 1ΛΌ, in some embodiments, criticality recovery in block 62 may include removing at least a portion of the neutron-absorbing material from the reactor core in block 64.

In some embodiments, if we refer further to FIG. 1AE, in block 66, a traveling wave nuclear reactor may be stopped before the controlled movement of selected nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places. Turning further to FIG. 1LR. At a block 68, a traveling wave nuclear reactor can be restarted after a controlled movement of selected nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places.

Turning now to FIG. 2A and 1B. An illustrative method 200 is provided for controlling a traveling wave nuclear reactor in which the combustion front 22 of a traveling nuclear fission wave propagates along the first and second measurements. Method 200 begins at block 202. At block 204, the desired shape of the burning front of the nuclear fission traveling wave along the second dimension in

- 16,024,235 fuel subassemblies 14 of nuclear fission in accordance with the selected set of dimensional restrictions. At a block 206, the movement of the selected nuclear fission subassemblies 14 along the first measurement from the respective first locations to the corresponding second locations is determined, depending on the desired shape.

Turning further to FIG. 2B, in some embodiments, at block 210, an existing shape of the burning front of a nuclear fission traveling wave is determined. It is clear that the determination of the existing shape of the nuclear fission traveling wavefront 22 in block 210 may be performed as required to determine the desired shape of the nuclear fission traveling wavefront 22 in block 204. In some embodiments, the determination of the existing shape of the traveling wavefront 22 is nuclear fission in block 210 can be performed before determining the desired shape of the front of burning 22 nuclear fission traveling wave in block 204. In some other embodiments, the implementation of the definition of the existing form the nuclear fission traveling wave burning front 22 in block 210 can be performed almost simultaneously with determining the desired shape of the nuclear fission traveling wave burning front 22 in block 204. In some other embodiments, the existing shape of the nuclear fission traveling wave burning front 22 in block 210 can be determined after determining the desired shape of the burning front of the nuclear fission traveling wave in block 204. The desired shape can be determined as required, including determining the fission rate, estimated burnup , reproduction rate, temperature distribution, energy density distribution, history of assembly operation and reactivity of displaced nuclear fuel in appropriate places.

It is clear that the selected nuclear fission fuel assemblies 14 can be moved for any purpose as required for a particular application, for example, to establish the desired shape of the nuclear fission traveling wave front 22 and / or to maintain the desired shape of the nuclear fission traveling wave front 22. . For example, in some embodiments, if we refer further to FIG. 2C, determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places, depending on the desired shape, in block 206 may include determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape, in block 212. In some other embodiments, if we refer further to FIG. 2Ό, determining the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places, depending on the desired shape, may include determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places so that maintain the desired shape in block 214.

It is clear that it may be necessary to determine, among other things, the time when to perform the required movement. For this purpose and if we turn to FIG. 2E, in some embodiments, in block 216, determining the time when to move the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first locations to the corresponding second locations is performed depending on the desired shape. It is also clear that the determination in block 216 can be performed at any time during the implementation of method 200, as required.

In some embodiments, the selected nuclear fission fuel assemblies 14 can be moved. Turning further to FIG. 2P. At a block 218, selected nuclear fission fuel assemblies 14 may move along a first measurement from respective first places to corresponding second places depending on the desired shape.

It is clear that some aspects of method 200 are similar to some of the aspects of method 10 that are explained above. These similar aspects will be mentioned, but for brevity there is no need to re-explain their details for understanding.

For example, if we turn in addition to FIG. 1B, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension. The first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. The first dimension and the second dimension can be almost orthogonal to each other.

In further examples and still referring in addition to FIG. 1B, the first dimension may be a radial dimension, and the second dimension may be an axial dimension. In some other examples, the first dimension may be an axial dimension, and the second dimension may be a radial dimension. Nuclear fission reactors of any type may contain nuclear fission fuel subassemblies that span the entire axial dimension, with several nuclear fission fuel subassemblies that span a radial measurement. A traveling nuclear fission wave can propagate along and along the axial measurement at a different speed than in the radial measurement, depending on the distribution of the energy density and divergence (deviations), in this case, a traveling nuclear fission wave from internal zones to external zones , especially in designs with a cylindrical reactor core. In this case, it is required to perform radial movements of the nuclear fission fuel subassemblies in order to preserve the waveform and characteristics in the axial dimension. For example, the propagation of a traveling nuclear fission wave within the axis of the reactor zone will contribute to neutron leakage from the reactor core at the axial ends of the reactor core. This leak, as described above, reduces the conversion of reproducing nuclei to fissile in a nuclear fission reactor. The nuclear fission fuel subassemblies with a combustion front that propagates to undesirable axial locations can be radially moved so that the nuclear fission fuel subassemblies undergo neutron activity in places in the nuclear fission fuel subassembly that reduce and (or) limit the further propagation of the combustion front to undesirable places. In other cases, it may be necessary to move the nuclear fission fuel subassemblies radially based on the propagation of the nuclear fission traveling wave in the axial dimension so that fissile material reproduced in the axial regions of the nuclear fission fuel subassembly can be used in other parts of the core of the nuclear fission reactor. At this axial location, the combustion front can be made non-uniform in radial measurement by controlled movement of the fuel fission subassemblies of nuclear fission so that, if necessary, alternative zones of changing enrichment could be created in this. The location of high enrichment zones near the spent or depleted fuel zones increases neutron leakage from high enrichment zones to low enrichment zones, thereby contributing to the conversion of the reproducing isotopic material into fissile material. It is clear that the aforementioned movements can be made to facilitate propagation in the first dimension, while limiting propagation in the second dimension.

In some other examples, if still referring further to FIG. 1B, the first dimension may be an axial dimension, and the second dimension may be a lateral dimension. In other examples, the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

As already noted, and if we turn in addition to FIG. 1C, the first places may be outwardly directed places 30 and the second places may be inwardly directed places 32. And as already noted, the inwardly directed places 32 and outwardly directed places 30 may be based on the geometric proximity to the central part of the reactor core 12. Inwardly directed locations 32 and outwardly directed locations 30 may be based on a neutron flux such that the neutron flux in inwardly directed locations 32 is greater than the neutron flux in outwardly directed locations 30. As already noted, inwardly directed locations 32 and outwardly directed locations 30 can be based on reactivity so that the cell in the inwardly directed places 32 is higher than the kegel in the outwardly directed places 30.

In some embodiments, if we refer further to FIG. 1Ό, the first places may be inwardly directed places 32 and the second places may be outwardly directed places 30. The inwardly directed places and outwardly directed places may be based on the geometric proximity to the central part of the reactor core 12, and (or) based on the neutron flux so that the neutron flux in the inwardly directed places is greater than the neutron flux in the outwardly directed places, and (or) be based on reactivity so that to _eGGes41e in the inwardly directed places is higher than to _{eG Ges11ue} in outward directed places.

In some embodiments, and as shown in FIG. 1B, first places and second places may be located on opposite sides of the reference value along the first measurement.

As also shown in FIG. 1B, in some embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may include a geometric proximity to the central region of the reactor core 12, a neutron flux, and / or reactivity.

In some embodiments, if we refer further to FIG. 20, determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the respective first places to the corresponding second locations in block 206 may include determining the rotation of at least one of the selected nuclear fission fuel subassemblies 14 in block 220. In some embodiments, if we refer further to FIG. 2H, determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 206 may include determining that at least one of the selected nuclear fission fuel assemblies 14 is turned over in block 222.

In some embodiments, a selected set of dimensional constraints may include a predetermined maximum distance along a second dimension. In some other embodiments, the selected set of dimensional constraints is a function of at least one of the criteria of the combustion front. For example, a combustion front criterion may include a neutron flux, such as an unlimited neutron flux associated with at least one of the selected heat-separating subassemblies 14. As yet another example, a combustion front criterion may include a neutron fluence, such as, without limitation , neutron fluence associated with at least one of the selected nuclear fission subassemblies 14. As another example, a combustion front criterion may include burnout, such as unlimited burnout associated with at least one of the selected nuclear fission fuel assemblies 14. In some other embodiments, the implementation of the criterion of the combustion front may include the location of the combustion front in at least one of the selected nuclear fission subassemblies 14.

Turning further to FIG. 2Ι. In some embodiments, determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second locations in block 206 may include determining the radial movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first locations to the corresponding second locations in the block 224. In some embodiments, if we refer further to FIG. 21, determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 206 may include determining the spiral movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places in block 226. In some other embodiments, if we refer further to FIG. 2Κ, determining the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first places to the corresponding second places in block 206 may include determining the axial movement of the selected nuclear fission fuel assemblies 14 in block 228.

Turning further to FIG. 2b. In some embodiments, determining the desired shape of the nuclear fission traveling wavefront 22 in block 204 may include determining the substantially spherical shape of the nuclear fission traveling wavefront 22 in block 230. In some other embodiments, referring further to FIG. 2M, determining the desired shape of the nuclear fission traveling wavefront 22 along the second dimension in block 204 may include determining the shape of the continuously curved surface of the nuclear fission traveling wavefront 22 in block 232. In some other embodiments, the curved surface may be such as to increase the area surface of the combustion front. In these embodiments, neutron leakage from the combustion zones to the reproduction zones is enhanced.

The desired shape of the combustion front 22 of the traveling wave of nuclear fission can be any. As already noted, in various embodiments, the desired shape of the combustion front 22 of the traveling wave of nuclear fission can be practically axisymmetric with respect to the second dimension; the required shape of the combustion front 22 of the traveling wave of nuclear fission can have almost n-fold axial symmetry with respect to the second dimension; the desired shape of the combustion front 22 of the traveling wave of nuclear fission may be asymmetric; and (or) the desired shape of the combustion front 22 of the traveling wave of nuclear fission can be axisymmetric with respect to the second dimension. In some other embodiments, symmetrical n-fold symmetry forms can be converted to separate combustion zones in the active zone of a traveling wave nuclear reactor. For example, a combustion front can transform into petals that propagate into n or fewer separate (i.e., neutron-free) combustion zones (see FIG. IV).

Some embodiments may be presented as illustrative systems. For example, as shown in FIG. 3A, an illustrative system 300 is provided for determining the movement of fuel nuclear fission subassemblies (not shown in FIG. 3A). As one non-limiting example, system 300 may provide a suitable system environment for implementing method 200 (FIGS. 2A-2M). In some embodiments, if we refer further to FIG. 1B, for a burning front of a nuclear fission traveling wave propagating in the first and second dimensions, electrical circuits 302 are provided to determine the desired shape of a burning front of a nuclear fission traveling wave 22 along the second dimension in the nuclear fission fuel subassemblies 14 in accordance with the selected set of dimensional restrictions. Electrical circuits 304 are provided for determining the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

In a general sense, specialists will understand that the various aspects described in this document, which can be implemented separately and (or) together, with a variety of hardware, types of software, software and hardware and / or any combination thereof, can be considered as consisting of various types of electrical circuits. Therefore, in the sense in which it is used in the present description, the term electrical circuits includes, without limitation, electrical circuits having at least one discrete electrical circuit; electrical circuits having at least one integrated circuit; electrical circuits having at least one specialized integrated circuit; electrical circuits forming a universal computing device configured by a computer program (for example, 19 024235 example, a universal computer configured by a computer program that at least partially implements the processes and / or devices described herein, or a microprocessor configured by a computer a program that at least partially implements the processes; and (or) the devices described herein); electrical circuits forming a storage device (for example, types of memory (for example, random access memory, flash memory, read-only memory, etc.)); and (or) electrical circuits forming a communication device (for example, a modem, communication switch (switch), optoelectric equipment, etc.). Those skilled in the art will understand that the subject matter described herein may be implemented in analog or digital form or in some combination thereof.

Turning further to FIG. 3B. In one illustrative example, electrical circuits 302 and / or electrical circuits 304 may be implemented as a computing system 306 (which may also be referred to as a host computer or host system). In the illustrated embodiment, a central processing unit (SRI) (or microprocessor) 308 is connected to the system bus 310. Random access memory (ΚΑΜ) 312 is connected to the system bus 310 and provides the SRI 308 with access to the storage device 314 (which can be used to store data related with one or more parameters of the combustion front 22 of the traveling wave of nuclear fission). When executing programmed commands, SRI 308 remembers these process steps in ΚΑΜ 312 and executes stored process steps from ΚΑΜ 312.

Computing system 306 may be connected to a computer network (not shown) using a network interface 316 and through a network connection (not shown). One such network is the Internet, which allows computing system 306 to download an application, code, documents, and other electronic information.

Permanent storage device (ΚОΜ) 318 is provided for storing invariant sequences of commands, such as sequences of start commands or sequences of the basic operating system of input-output (VU8).

The input / output device interface (Ι / О) 320 allows the computing system 306 to connect to various input / output devices, for example, a keyboard, pointing device (mouse), monitor, printer, modem, and the like. The I / O device interface 320 is shown as a single unit for simplicity, but may be several interfaces for interfacing with various types of I / O devices.

It is clear that the embodiments are not limited to the architecture of the computing system 306 shown in FIG. 3B. Depending on the type of business application / environment, the computing system 306 may have more or fewer components. For example, computing system 306 may be a set top box, laptop, laptop, desktop system, or other types of systems.

In various embodiments, portions of the disclosed systems and methods include one or more computer program products. A computer program product includes a computer-readable storage medium, such as a non-volatile storage medium, and portions of a computer-readable control program, such as a set of computer programs embodied in a computer-readable storage medium. Typically, a computer program is stored and executed by a processor or associated storage device, such as the processing components shown in FIG. 3B.

In this regard, FIG. 2A-2M and 3A-3C are flowcharts of methods, systems, and software products, respectively, in accordance with various embodiments. It is understood that each block of flowcharts and combinations of blocks in flowcharts can be implemented by computer program instructions. These commands of computer programs can be loaded into a computer or other programmable device to create a mechanism so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated in the block diagram (block diagrams). These commands of computer programs can also be loaded into computer-readable memory, which can command a computer or other programmable device to act in a specific way, so that instructions stored in computer-readable memory create an article, including command means that implement the function indicated on the block diagram (flowcharts). These computer program instructions can also be downloaded to a computer or other programmable device to ensure that a number of operational steps are performed on a computer or other programmable device, to create a computer-implemented process so that instructions that are executed by a computer or other programmable device create stages for implementing functions indicated on the flowchart (flowcharts).

Accordingly, the blocks of the flowchart support combinations of means for performing the specified functions, combinations of stages for performing the specified functions and software command means for performing the specified functions. It is also clear that each block of the block diagram and combinations of blocks in the block diagram (block diagrams) can be implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine commands.

Turning further to FIG. 3C. In some embodiments, electrical circuits 304 may also be used to determine the existing shape of the burning front of a nuclear fission traveling wave. For example, sensors 322 may be operatively connected to electrical circuits 304 in a signal message via an appropriate input interface 324. Sensors 322 may include any suitable sensor that measures a specific parameter of the combustion front 22 of a traveling nuclear fission wave. For example, sensors 322 can measure neutron flux, neutron fluence, fading, and / or reactivity (or any component thereof).

As already noted, embodiments of the system 300 and circuitry 302 and 304 may be designed to create a suitable system environment for implementing method 200 (FIG. 2A2M) (regardless of whether computer program instructions are loaded into a computer or other programmable device to create a mechanism) so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated on the flowchart (flowcharts), or each block of the flowchart and combination of blocks on the block -scheme (Flowcharts) implemented by special computer systems based on the hardware that perform the specified functions or steps, or combinations of special hardware and computer instructions. Some features of embodiments of the system 300 will be discussed with reference further to FIG. 1Β-Ό, P, 1b, 1O, 10, 1P-1 \ U and 2A-2M.

To this end, in some embodiments, the electrical circuits 304 may also be used to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape. The electrical circuits 304 may also be used to determine the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape. Electrical circuits 304 can also be used to determine the time by moving the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

As already noted, in some embodiments, the nuclear fission fuel assemblies 14 may be elongated along the second dimension.

As already noted, in some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some other embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first locations may be outwardly directed locations 30, and the second locations may be inwardly oriented locations 32. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on various attributes as desired, such as, without limitation, geometric proximity to the central part of the reactor core 12, a neutron flux (so that the neutron flux in inwardly directed places 32 is greater than the neutron flux in outwardly directed places 30), and (or) reactivity (so that Καούνε in inwardly directed places 32 is higher than 1 < _ΧΒχιν in outwardly directed places 30.

In some other embodiments, the first locations may be inwardly directed locations 32, and the second locations may be outwardly oriented locations 30. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on various attributes as desired, such as, without limitation, geometric proximity to the central part of the reactor core 12, neutron flux (so that the neutron flux in inwardly directed places 32 is greater than the neutron flux in outwardly directed places 30 ), and (or) reactivity (in such a way that k _e and _ec c> / _e in the inwardly directed places 32 are higher than _{kep e} |, '., - _e in the outwardly directed places 30). In some embodiments, the first places and second places may be on opposite sides of the initial value along the first dimension.

In some other embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may be a geometric proximity to the central region of the reactor core 12, a neutron flux, and / or reactivity.

In some embodiments, electrical circuits 304 may also be used to determine the rotation of at least one of the selected nuclear fuel subassemblies 14

- 21,024,235 divisions. In some other embodiments, electrical circuits 304 may also be used to determine the inversion of at least one of the selected nuclear fission fuel assemblies 14.

As already noted, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension.

In some other embodiments, the implementation of the selected set of dimensional restrictions may be a function of at least one criterion of the combustion front. For example, a combustion front criterion may include, without limitation, a neutron flux, such as a neutron flux, associated with at least one of the selected nuclear fission fuel assemblies 14; a neutron fluence, such as a neutron fluence, associated with at least one of a selected nuclear fission fuel subassembly 14; and / or burnout, such as burnout associated with at least one of the selected nuclear fission fuel assemblies 14. In some embodiments, the burning front criterion may include the location of the burning front in at least one of the selected nuclear fission fuel assemblies 14.

In some embodiments, electrical circuits 304 may also be used to determine the radial movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the respective first locations to their respective second locations. The electrical circuits 304 may also be used to determine the spiral movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places. Electrical circuits 304 can also be used to determine the axial displacement of selected nuclear fission subassemblies 14.

In some embodiments, electrical circuits 302 can also be used to determine the almost spherical shape of the combustion front 22 of a traveling nuclear fission wave. Electrical circuits 302 can also be used to determine the shape of a continuously curved surface of the combustion front 22 of a traveling nuclear fission wave.

In various embodiments, the desired shape of the burning front of the nuclear fission traveling wave may be substantially axisymmetric with respect to the second dimension; may have practically η-fold axial symmetry with respect to the second dimension; and / or may be asymmetric, for example, without limitation, axisymmetric with respect to the second dimension.

As another example, if we turn now to FIG. 4A, another illustrative system 400 is provided for moving fuel nuclear fission subassemblies (not shown in FIG. 4A). As one example, not limiting the scope of the present invention, system 400 may provide a suitable system environment for implementing method 100 (FIGS. 1Α-1ΑΡ). Accordingly, the following description is given with further reference to FIG. 1Α-1ΑΡ.

In some embodiments, for a burning front of a nuclear fission traveling wave propagating in the first and second dimensions, electrical circuits 402 are used to determine the desired shape of a burning nuclear fission wave front 22 along a second dimension in the nuclear fission fuel subassemblies 14 in accordance with the selected dimensional set restrictions. The electrical circuits 404 are intended to determine the movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape. The subassembly 405 is designed to move the selected nuclear fission fuel assemblies 14 responsive to the electrical circuits 404.

It is clear that the electrical circuits 402 and 404 may be similar to the electrical circuits 302 and 304. In some cases, the electrical circuits 402 and 404 may be the same as the electrical circuits 302 and 304. Therefore, for brevity, it is not necessary to repeat the details for understanding. .

As a brief overview, if we turn further to FIG. 4B, in an illustrative example, electrical circuits 402 and / or electrical circuits 404 may be implemented as a computing system 406 (which may also be referred to as a host computer or host system). In the illustrated embodiment, a central processing unit (SRI) (or microprocessor) 408 is connected to the system bus 410. Random access memory (ΚΑΜ) 412 is connected to the system bus 410 and provides the SRI 408 with access to the storage device 414 (which can be used to store data related with one or more parameters of the combustion front 22 of a traveling wave of nuclear fission). When executing programmed commands, SRI 408 stores these process steps in ΚΑΜ 412 and executes stored process steps from из 412. Computing system 406 can be connected to a computer network (not shown) using a network interface 416 and through a network connection (not shown). Permanent storage device (KΟΜ) 418 is provided for storing invariant sequences of commands, such as sequences of start commands or sequences of the basic operating system of input-output (VU8). The interface of input / output devices (Ι / О) 420 allows the computer system 406 to connect to various input / output devices, for example, a keyboard, pointing device (mouse), monitor, printer, modem, etc. Clearly, the embodiments are not limited to the architecture of the computing system 406 shown in FIG. 4B. The description of the non-limitation regarding the computing system 306 (FIG. 3B) extends to the computing system 406.

In various embodiments, portions of the disclosed systems and methods include one or more computer program products. The above description regarding computer software products associated with system 300 (FIG. 3A) applies to system 400 as well.

In this regard, FIG. 1A, 11, 1K, 1Μ-1Ν, 1P, 1X-1AP and 4A-4C are flowcharts of methods, systems, and software products in accordance with various embodiments. It is understood that each block of flowcharts and combinations of blocks in flowcharts can be implemented by computer program instructions. These commands of computer programs can be loaded into a computer or other programmable device to create a mechanism so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated in the block diagram (block diagrams). These commands of computer programs can also be loaded into computer-readable memory, which can command a computer or other programmable device to act in a specific way, so that instructions stored in computer-readable memory create an article, including command means that implement the function indicated on the block diagram (flowcharts). These commands of computer programs can be loaded into a computer or other programmable device to ensure that a number of operational steps are performed on a computer or other programmable device, to create a computer-implemented process, so that the commands that are executed by a computer or other programmable device create stages for implementing functions, indicated on the flowchart (flowcharts).

Accordingly, the blocks of the flowchart support combinations of means for performing the specified functions, combinations of stages for performing the specified functions and software command means for performing the specified functions. It is also clear that each block of the block diagram and combinations of blocks in the block diagram (block diagrams) can be implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine instructions.

Turning further to FIG. 4C. In some embodiments, electrical circuits 404 can also be used to determine the existing shape of the burning front of a nuclear fission traveling wave. For example, the sensors 422 can be functionally connected to the electrical circuits 404 in a signal message via the corresponding input interface 424. The electrical circuits 404, the sensors 422 and the input interface 424 can be similar (and in some cases identical) to the electric circuits 304, sensors 322 and the input interface 324 (all in FIG. 3C). To understand the repetition of their details is not required.

As already noted, embodiments of the system 400, electrical circuits 402 and 404, and subassemblies 405 may be designed to create a suitable system environment for implementing method 100 (FIGS. 1A, 11, 1K, 1Μ-1Ν, 1P, and 1X-1AP), regardless whether computer program instructions are loaded into a computer or other programmable device to create a mechanism so that the commands that are executed on a computer or other programmable device create means for implementing the functions indicated on the block diagram (block diagrams), or each block block -from Schemes and combinations of blocks on a block diagram (block diagrams) were implemented by special computer systems based on hardware that perform the specified functions or stages, or by combinations of special hardware and machine instructions. Some features of embodiments of the system 400 will be discussed with reference further to FIG. 1A-1AP.

In some embodiments, as shown in FIG. 4C, electrical circuits 404 can also be used to determine the existing shape of the combustion front 22 of a traveling nuclear fission wave. This determination can be made in a similar or identical manner as in the case of electrical circuits 304 (FIG. 3A), as described above. To this end, the sensors 422 and the input interface 424 are similar or (in some cases) identical to the sensors 322 and the input interface 324 in FIG. 3C. Sensors 422, input interface 424, and circuitry 404 interact, as already noted for sensors 322, input interface 324, and circuitry 304 (all in FIG. 3C).

In some embodiments, electrical circuits 404 may also be used to determine the movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places so as to establish the desired shape. In some other embodiments, electrical circuits 404 may also be used to determine the movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first locations to corresponding second locations so as to maintain a desired shape.

In some embodiments, electrical circuits 404 may also be used to determine when to move selected nuclear fission subassemblies 14 along a first measurement from respective first places to corresponding second places depending on the desired shape.

In some embodiments, nuclear fission subassemblies 14 may

- 23,024,335 to be elongated along the second dimension. The first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. The first dimension and the second dimension can be almost orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first locations may be outwardly directed locations 30, and the second locations may be inwardly oriented locations 32. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on: geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30, and (or) the reactivity so that k _{e [} | _{es1 | ye} in the inwardly directed places 32 is higher than to _{e £ £ es41yue} in the outwardly directed places 30.

In some other embodiments, the first locations may be inwardly directed locations 32, and the second locations are outwardly oriented locations 30. Inwardly directed locations and outwardly oriented locations may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30, and (or) the reactivity so that k _{e £ £ ec £ 1te} in the inwardly directed places 32 is higher than k _{e £ ec1 |} , _{; e} in outward places 30.

In some embodiments, the first places and second places may be on opposite sides of the initial value along the first dimension.

In some other embodiments, the first places and second places may include at least one attribute that is substantially equal. For example, at least one attribute may include a geometric proximity to the central region of the reactor core 12; neutron flux; and / or reactivity.

In various embodiments, electrical circuits 404 may also be used to determine the rotation of at least one of the selected nuclear fission subassemblies 14. Electrical circuits 404 may also be used to determine the reversal of at least one of the selected nuclear fission subassemblies 14.

The subassembly 405 may include any known suitable nuclear fuel handling device, such as, but not limited to, a nuclear fuel handling device located in the core. However, in some other embodiments, subassembly 405 may include a nuclear fuel handling device located outside the core.

Regardless of the form in which subassembly 405 is embodied, in various embodiments, subassembly 405 can also be used to radially move selected nuclear fission fuel assemblies 14 from respective first places to corresponding second places. The subassembly 405 may also be intended for the helical movement of the selected nuclear fission fuel assemblies 14 from the corresponding first places to the corresponding second places. The subassembly 405 may also be intended for axial movement of the selected nuclear fission fuel subassemblies.

In some embodiments, subassembly 405 may also be designed to rotate selected nuclear fission subassemblies 14. In some other embodiments, subassembly 405 can also be used to flip selected nuclear fission subassemblies 14. Turning now to FIG. 5. In various embodiments, an illustrative traveling wave 500 nuclear reactor may be provided. A traveling wave 500 nuclear reactor includes an active region 12 of a traveling wave nuclear reactor. As already noted, the fuel subassemblies 14 of nuclear fission are received in the active zone 12 of a traveling wave nuclear reactor. Each of the nuclear fission fuel subassemblies 14 is designed to propagate in it a combustion front 22 of a traveling nuclear fission wave along the first and second dimensions. The electrical circuits 402 are designed to determine the desired shape of the combustion front 22 of the traveling nuclear fission wave along the second dimension in the nuclear fission fuel subassemblies 14 in accordance with the selected set of dimensional restrictions. The electrical circuits 404 are designed to determine the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape. The subassembly 405 is designed to move the selected nuclear fission fuel assemblies 14 responsive to the electrical circuits 404.

Thus, the reactor 500 can be configured as the reactor core 12 described above in combination with and interacting with the system 400 also described above. Since the details regarding

- 24,024,235 of the core 12 of the reactor (and its components) and the system 400 (and its components) are described above, it is not necessary to repeat them for understanding.

As already noted, in various embodiments, electrical circuits 404 can also be used to determine the existing shape of the combustion front 22 of a traveling nuclear fission wave. The electrical circuits 404 can also be used to determine the movement of the selected nuclear fission fuel assemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape. The electrical circuits 404 may also be used to determine the movement of the selected nuclear fission subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

As already noted, in some embodiments, the electrical circuits 404 can also be used to determine the time when to move the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

In some embodiments, the nuclear fission fuel assemblies 14 may be elongated along a second dimension.

In some embodiments, the first measurement may be substantially orthogonal to the elongated axis of the nuclear fission subassemblies 14. In some embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension may be a radial dimension, and the second dimension may be an axial dimension; the first dimension may be an axial dimension, and the second dimension may be a radial dimension; the first dimension may be an axial dimension, and the second dimension may be a lateral dimension; and / or the first dimension may be a lateral dimension, and the second dimension may be an axial dimension.

In some embodiments, the first locations may be outwardly directed locations 30, and the second locations are inwardly oriented locations 32. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30; and (or) reactivity so that k _{e [1ec1 | уе} in the inwardly directed places 32 is higher than к _{е £$ ес41уе} in the outwardly directed places 30.

In some other embodiments, the first locations may be inwardly directed locations 32, and the second locations may be outwardly oriented locations 30. Inwardly directed locations 32 and outwardly oriented locations 30 may be based on the geometric proximity to the central portion of the reactor core 12; the neutron flux so that the neutron flux in the inwardly directed places 32 is greater than the neutron flux in the outwardly directed places 30; and (or) reactivity so that k _{e £ £ £ £ те те те} in the inwardly directed places 32 is greater than k _{e [1 1 | е е} in outwardly directed places 30.

In some embodiments, the first places and second places may be on opposite sides of the reference value along the first dimension.

In some embodiments, the first places and second places may include at least one attribute that is substantially equal. At least one attribute may include geometric proximity to the central region of the reactor core 12, neutron flux, and / or reactivity.

In various embodiments, and as already noted, electrical circuits 404 can be used to determine the rotation of at least one of the selected nuclear fission subassemblies 14 and / or to be used and to determine the reversal of at least one of the selected nuclear fission fuel subassemblies 14.

In some embodiments, a selected set of dimensional constraints may include a predetermined maximum distance along a second dimension. In some other embodiments, the implementation of the selected set of dimensional constraints may be a function of at least one criterion for the combustion front, such as, without limitation, a neutron flux, such as a neutron flux associated with at least one of the selected nuclear fission fuel assemblies 14; a neutron fluence, such as a neutron fluence, associated with at least one of a selected nuclear fission fuel subassembly 14; and / or burnout, such as burnout associated with at least one of the selected nuclear fission fuel assemblies 14. In some other embodiments, the implementation of the criterion of the combustion front may include the location of the combustion front in at least one of the selected nuclear fission subassemblies 14.

In various embodiments, electrical circuits 404 can also be used to determine the radial movement of selected nuclear fission fuel subassemblies 14 along a first measurement from respective first places to corresponding second places. Electrical circuits 2504235 may also be used to determine the spiral movement of the selected nuclear fission fuel subassemblies 14 along the first measurement from the corresponding first places to the corresponding second places.

Electrical circuits 404 can also be used to determine the axial displacement of selected nuclear fission subassemblies 14.

In various embodiments, electrical circuits 402 can also be used to determine the practically spherical shape of the burning front of a nuclear fission traveling wave 22 and (or) the shape of a continuously curved surface of a burning front 22 of a nuclear fission traveling wave. The desired shape of the combustion front 22 of the traveling wave of nuclear fission can be practically axisymmetric with respect to the second dimension; can have almost n-fold axial symmetry relative to the second dimension; and / or may be asymmetric, such as axisymmetric with respect to the second dimension.

In some embodiments, subassembly 405 may include a nuclear fuel handling device. As already noted, subassembly 405 may include any known suitable nuclear fuel handling device, such as, but not limited to, a nuclear fuel handling device located in the core. However, in some other embodiments, subassembly 405 may include a nuclear fuel handling device located outside the core.

In addition, as already noted, in various embodiments, subassembly 405 can also be used to radially move selected nuclear fission subassemblies 14 from respective first places to corresponding second places. The subassembly 405 may also be intended for the helical movement of the selected nuclear fission fuel assemblies 14 from the corresponding first places to the corresponding second places. The subassembly 405 may also be intended for axial movement of the selected nuclear fission fuel assemblies 14. The subassembly 405 can also be used to rotate the selected nuclear fission subassemblies 14. The subassembly 405 can also be used to invert selected nuclear fission subassemblies 14.

Turning now to FIG. 6A. In some embodiments, a method 600 is provided for controlling a traveling wave nuclear reactor. Method 600 begins at block 602. Turning further to FIG. 1B. At a block 604, at least one nuclear fission fuel assembly 14 is moved outward from a first place in a running wave nuclear reactor 12 to a second place in a running wave nuclear reactor 12. Method 600 is stopped at block 606.

In some embodiments, if we refer further to FIG. 6B, at block 608, at least one nuclear fission fuel assembly 14 may be moved inward from a second location.

In various embodiments, the first space and the second space may be based on geometric proximity to the central portion of the core 12 of the reactor neutron flux so that the flux in the first field of neutrons is greater than the neutron flux in the second field, and reactivity so that a _eGGes zu _e in the first places more than к _{е [1ес1 |} ,. _e in second places.

Turning now to FIG. 7. In some embodiments, a method 700 is provided for controlling a traveling wave nuclear reactor. Method 700 starts at block 702. Turning further to FIG. 1B. At a block 704, the movement of at least one nuclear fission assembly 14 in a first direction from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12 is determined. Second place is different from first place. At a block 706, movement of at least one nuclear fission assembly 14 in a second direction from a second location is determined. The second direction is different from the first direction. Method 700 is stopped at block 708.

In some embodiments, the first direction may be outward and the second direction may be inward. The first places and second places can be based on various attributes or parameters, such as, without limitation, the geometric proximity to the central part of the reactor core 12, the neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity so that k _{e [1es1 |} ,. _e in the first places more than to _eGGes41ue in the second places.

In some other embodiments, the first direction may be inward and the second direction may be outward. Second places and first places can be based on various attributes or parameters, such as, without limitation, the geometric proximity to the central part of the reactor core 12, the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places, and ( or) reactivity so that k _{e [1ec1 | ye} in the second places is greater than k _{e [1ec1 | ye} in the first places.

Turning now to FIG. 8. In some embodiments, a method 800 is provided for controlling a traveling wave nuclear reactor. Method 800 begins at block 802. Turning further to FIG. 1B. At block 804, at least one nuclear fission fuel assembly 14

- 26,024,235 are moved in the first direction from the first place in the active zone 12 of the traveling wave nuclear reactor to the second place in the active zone 12 of the traveling wave nuclear reactor. Second place is different from first place. At a block 806, movement of at least one nuclear fission assembly 14 in a second direction from a second location is determined. The second direction is different from the first direction. Method 800 is stopped at block 808.

In some embodiments, the first direction may be outward and the second direction may be inward. The first places and second places can be based on various attributes or parameters, such as, without limitation, the geometric proximity to the central part of the reactor core 12, the neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity in such a way that k _{e £ ес £ £ £ у е е} in the first places is greater than k _{£ £ ес 1 1 | у вторых вторых} in the second places.

In some other embodiments, the first direction may be inward and the second direction may be outward, second places and first places may be based on various attributes or parameters, such as, without limitation, geometric proximity to the central part of the reactor core 12, neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places, and (or) the reactivity so that k _{e £ ес 1 те те} in the second places is greater than k _{£ £ £ £ е 1} in the first places.

Turning now to FIG. 9. In some embodiments, a method 900 is provided for controlling a traveling wave nuclear reactor. Method 800 begins at block 902. Turning further to FIG. 1B. At a block 904, at least one nuclear fission fuel assembly 14 is moved in a first direction from a first place in a traveling wave nuclear reactor 12 to a second place in a traveling wave nuclear reactor 12. Second place is different from first place. At a block 906, at least one nuclear fission fuel assembly 14 is moved in a second direction from a second location. The second direction is different from the first direction. Method 900 is stopped at block 908.

In some embodiments, the first direction may be outward and the second direction may be inward. The first places and second places can be based on various attributes or parameters, such as, without limitation, the geometric proximity to the central part of the reactor core 12, the neutron flux so that the neutron flux in the first places is larger than the neutron flux in the second places, and ( or) reactivity so that k _{e £ £ 1 у е е} in the first places is greater than k _{£ £ ес 41 41 41 у е е вторых} in the second place.

In some other embodiments, the first direction may be inward and the second direction may be outward. Second places and first places can be based on various attributes or parameters, such as, without limitation, the geometric proximity to the central part of the reactor core 12, the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places, and ( or) reactivity so that k _{e £ ес ес £ £ те те} in the second places is greater than k _{£ £ ес £ £ 1 е е} in the first places.

Turning now to FIG. 10A. In some embodiments, a method 1000 is provided for controlling a traveling wave nuclear reactor. Method 1000 begins at block 1002. At block 1004, a predetermined burnup level is selected. In block 1006, the movement of the selected nuclear fission fuel assemblies in the core of the nuclear reactor is determined so as to achieve a burnup level equal to a predetermined burnup level in virtually all nuclear fission fuel assemblies. Method 1000 is stopped at block 1008.

Turning further to FIG. 10B. In some embodiments, at block 1010, the selected nuclear fission fuel assemblies may be moved in the core of the nuclear fission reactor in accordance with the determined movement.

Turning further to FIG. 10C. In some embodiments, block 1012 may determine the extraction of the respective selected nuclear fission fuel assemblies when the burnup level is equal to a predetermined burnup level.

Turning further to FIG. 10Ό, in some embodiments, at block 1014, selected nuclear fission fuel assemblies may be removed in accordance with a specific recovery.

In this application, formal headings are used for clarity of presentation. It should be understood, however, that these headers serve the purpose of presentation, and that various types of subject matter may be considered in the application (e.g., device (s) / structure (s) may be considered under the heading (s) of method (s) / operations, and (or) the method (s) / operations may be considered under the headings of a design (s) / process (s); and (or) descriptions of individual topics may cover two or more thematic headings). Therefore, the use of formal headings is not intended to limit the scope of the present invention in any way.

Those skilled in the art will understand that the above specific exemplary methods and / or devices and / or technologies are more general methods and / or devices and / or technologies whose ideas are expressed elsewhere in the present description, such as in the claims filed with the present description, and (or) elsewhere in this application.

Experts know that the level of technology has reached a level at which a small difference remains between the implementation of aspects of the system with hardware, software and (or) software and hardware; the use of hardware, software and (or) firmware is usually (but not always, due to the fact that in some contexts the choice between hardware and software can become significant) is a design solution that represents a compromise between cost and effectiveness . Professionals know that there are various means by which processes can be carried out, and (or) systems, and (or) other technologies described in this document (for example, hardware, software and (or) firmware), and that the preferred tool will vary depending on the context in which the processes are used, and (or) systems, and (or) other technologies. For example, if the person implementing the plan gives priority to speed and accuracy, he may incline mainly to a tool based on hardware and (or) software and hardware; alternatively, if flexibility is given priority, the person implementing the plan may be inclined mainly to implement software; or, again, alternatively, the person implementing the plan may be inclined to some combination of hardware, software, and (or) software and hardware. Therefore, there are several possible means by which processes can be carried out, and (or) devices, and (or) other technologies described herein, and none of the means is inherently superior to the other in the sense that any means for use is a choice depending on the context in which this tool will be used and the specific aspects (for example, speed, flexibility or predictability) that concern the person implementing the plan, any of which can vary Rova. It will be apparent to those skilled in the art that the optical aspects of the embodiments will typically use hardware, software, and / or optical-oriented hardware and software.

In some embodiments described herein, logical or similar implementations may include software control structures or other control structures. Electronic circuits, for example, may have one or more electric current paths constructed and arranged to perform various functions, as described herein. In some embodiments, one or more environments may be intended to carry an implementation detected by a device when these environments hold or transmit commands detected by a device intended to be executed as described herein. In some embodiments, for example, implementations may be updating or changing existing software, or firmware, or gate arrays, or programmable hardware, for example, by receiving or transmitting one or more commands in relation to one or more operations, described in this document. Alternatively or additionally, in some embodiments, the implementation may include components of special hardware, software, firmware, and / or universal components that execute or otherwise activate special components. Specifications or other implementations may be transmitted by one or more types of material transmission media, as described herein, optionally by packet transmission, or otherwise by passing through distributed media at different times.

Alternatively or additionally, implementations may include executing a special sequence of commands or activating circuits to enable, start, coordinate, query, or otherwise trigger one or more events of virtually any functional operations described herein. In some embodiments, operational or other logical descriptions herein may be expressed as source code and compiled or otherwise activated as an executable sequence of instructions. In some contexts, for example, implementations may be implemented, in whole or in part, by source code, such as C ++ code, or other code sequences. In other implementations, an implementation based on the source or code, being available in large quantities and (or) using known methods, can be compiled / implemented / translated / converted into a high-level descriptor language (for example, first the implementation of the described technologies in the C or C ++ programming language and then the transformation of the implementation in this programming language into the implementation in the language obtained by logical synthesis, the implementation in the hardware description language, the implementation by means of models knowledge of hardware design and (or) other similar method (s) of expression). For example, all or part of a logical expression (for example, an implementation in a programming language) can be performed as a hardware description in the USGPod language (for example, in a hardware description language (НОЬ) and (or) in a hardware description language for ultrafast integrated circuits (UNAI) ) or as another model of circuits, which can then be used to create a physical implementation that has hardware (for example, a specialized integrated circuit). Specialists will understand how to obtain, configure and optimize the appropriate transmitting and computing elements, material supplies, actuators or other designs in the light of these ideas.

The above description sets forth various embodiments of devices and / or processes using flow charts and / or examples. As far as these flowcharts and (or) examples contain one or more functions and (or) operations, specialists will understand that each function and / or operation on these flowcharts or in these examples can be implemented separately and (or) together , a variety of hardware, types of software, software and hardware and / or their almost any combination. In one embodiment, several parts of the subject matter described herein may be implemented using special integrated circuits (L81C8), operational programming logic matrices (RROLs), digital signal processing processors (ΌδΡδ), or other integrated formats. However, it is clear to those skilled in the art that certain aspects of the embodiments disclosed herein, in whole or in part, can equally be implemented in integrated circuits, as one or more computer programs run on one or more computers (for example, as one or more programs run on one or more computer systems), as one or more computer programs run on one or more processors (for example, as one or more programs run on one or more microprocessors), such as software and hardware, or almost any combination of them, and that the development of circuits and (or) writing code for software or software and hardware will be quite capable of specialists in the light of this disclosure. In addition, those skilled in the art will understand that the mechanisms of the subject invention described herein can be distributed as a software product in a variety of forms, and that the illustrative embodiment of the subject invention described herein is applicable regardless of the particular type of signal-carrying medium used for the actual implementation of the distribution. Examples of a signal carrier medium include, but are not limited to, a rewritable medium such as a floppy disk (diskette), hard disk, compact disc (CO), digital video disc (ΌνΌ), digital media tape, computer memory, etc. P.; and a transmission medium, such as a digital and / or analog communication medium (for example, a fiber optic cable, a waveguide, a wired communication channel, a wireless communication channel (for example, a transmitter, a receiver, transmission logic, reception logic, etc.) and etc.

In a general sense, those skilled in the art will understand that the various aspects described herein that can be implemented separately and (or) together by different types of electromechanical systems having a wide variety of electrical components, such as hardware, software, and hardware and software and (or) their almost any combination; and a variety of components that can exert mechanical force or impart movement, such as rigid bodies, spring or torsion bodies, hydraulic devices, devices with an electromagnetic drive and (or) almost any combination of them. Therefore, in the sense in which it is used in the present description, the term electromechanical system includes, without limitation, electrical circuits functionally connected to the transducer (for example, an actuator, an electric motor, a piezoelectric crystal, a microelectromechanical system (MEM8), etc.), electrical circuits having at least one discrete electrical circuit, electrical circuits having at least one integrated circuit, electrical circuits having at least one s a personalized integrated circuit, electrical circuits forming a universal computing device configured by a computer program (for example, a universal computer configured by a computer program that at least partially implements the processes and / or devices described herein, or a microprocessor configured by a computer a program that at least partially implements the processes and (or) devices described herein), electrical circuits, circuits indicating a storage device (for example, different types of memory (for example, random access memory, flash memory, read-only memory, etc.)), electrical circuits forming a communication device (for example, a modem, a communication switch (switch), optoelectric equipment and etc.) and (or) any non-electric analogue thereof, for example optical or other analogs. Those skilled in the art will also understand that examples of an electromechanical system include, but are not limited to, a wide variety of consumer electronics systems, medical devices, and other systems such as automobile transport systems, factory automation systems, security systems, and / or communications / computing systems. Those skilled in the art will understand that unless the context may dictate otherwise, the term electromechanical as used in the present description is not necessarily limited to a system having both an electric and a mechanical drive.

All of the aforementioned US patents, publications of US patent applications, US patent applications, patents of other countries, patent applications of other countries and non-patent publications referred to in 29,024,235 of the present description and / or listed in any application information sheet 511SS1), are hereby incorporated by reference in so far as they are consistent with it.

It will be apparent to those skilled in the art that the components described (eg, operations), devices, objects, and the discussion that accompany them are used as examples for clarity of concept, and that various modifications and changes to the design are possible. Therefore, the specific examples used in this document and the discussion that accompanies them are intended to represent their more general classes. In general, the use of any particular example is intended to represent its class, and not the inclusion of specific components (eg, operations), devices, and objects should not be construed as limiting the scope of the present invention.

As for the use in this document of virtually any terms in the plural and (or) singular, specialists can translate from the plural to the singular and (or) from the singular to the plural, as the context and (or) the application requires. For clarity, the various permutations of the singular / plural are not explicitly given in this document.

The subject matter described herein sometimes illustrates various components contained in or associated with other components. It should be understood that these described architectures are purely exemplary, and that many other architectures that achieve the same functionality can actually be implemented. In a conceptual sense, any arrangement of components to achieve the same functionality is effectively connected so that the required functionality is achieved. Therefore, any two components in this document, combined to achieve specific functionality, can be considered interconnected so that the desired functionality is achieved, regardless of architecture or intermediate components. Similarly, any two components connected in this way can be considered both operationally connected or operationally linked to each other to achieve the required functionality, and any two components that can be connected in this way can also be considered as which can be operationally linked to achieve the required functionality. Specific examples of components that can be operationally coupled include, but are not limited to, physically mating and / or physically interacting components, and / or wirelessly interacting and / or wirelessly interacting components, and / or logically interacting and / or Logically interoperate components.

Specific aspects of the subject matter described herein are shown and described above, but it is clear to those skilled in the art that, based on the above description, changes and modifications are possible within the spirit and scope of the subject of the present invention described herein and its broader aspects, and therefore, the appended claims should cover in their scope all of these changes and modifications within the spirit and scope of the subject matter of the present invention described herein. Those skilled in the art will understand that, in general, the terms used in this document, and especially in the attached claims (for example, in the text of the attached claims), are for the most part intended as open terms (for example, the term including should be interpreted as including without limitation, the term having should be interpreted as having at least the term includes should be interpreted as including without limitation, etc.). In addition, it will be clear to those skilled in the art that if a specific number of enumerations of the items presented is outlined, this intention will be clearly indicated in the claims, and in the absence of this enumeration, this intention is absent. For example, to aid understanding, the paragraphs of the following appended claims may include the use of at least one and one or more introductory phrases to represent a list of paragraphs. In addition, even the specific number of the enumeration of the items presented is indeed clearly mentioned, it is clear to specialists that this enumeration should usually be interpreted to mean at least the indicated number (for example, a simple enumeration of two enumerations without other modifiers usually means at least two enumerations or two or more listings). In addition, in cases where an expression similar to at least one of A, B and C, etc. is used, such a construction is usually intended in the sense in which one will understand this expression (for example, a system having at least at least one of A, B and C will include, without limitation, systems having only A, only B, only C, A and B together, A and C together, B and C together and (or) A, B and C together etc.). In those cases where an expression similar to at least one of A, B or C, etc. is used, usually such a construction is intended in the sense in which a specialist will understand this expression (for example, a system having at least one of A , B or C will include, without limitation, systems having only A, only B, only C, A and B together, A and C together, B and C together and (or) A, B and C together, etc.) . In addition, those skilled in the art will understand that usually a disjunctive word and / or phrase representing two or more alternative terms, whether in the description, claims, or in the drawings, should be understood as suggesting the possibility of including one of these terms, any of these terms, or both terms if context is not

- 30,024,235 dictates otherwise. For example, the phrase A or B will usually be understood as including the capabilities of A, or B, or A and B.

As for the attached claims, those skilled in the art will understand that the operations listed therein can usually be performed in any order. In addition, although various operating flows are presented in a specific sequence (s), it should be understood that various operations can be performed in different orders than those illustrated or can be performed simultaneously. Examples of these alternative orders may include overlapping, alternating, interrupted, reordered, incremental, preparatory, additional, simultaneous, reverse, or other variant orders, unless the context dictates otherwise. In addition, terms like responding to, related to, or other names of past adjectives are usually not intended to exclude these options, unless the context dictates otherwise.

Aspects of the subject matter described herein are set forth in the following numbered paragraphs.

1. A method of operating a nuclear reactor on a traveling wave, comprising the following stages: a stage in which the combustion front of a traveling wave of nuclear fission is distributed along the first and second measurements in several fuel subassemblies of nuclear fission in the active zone of a nuclear reactor on a traveling wave; and a stage in which the selected several nuclear fission fuel subassemblies are controllably moved along the first measurement from the corresponding first places to the corresponding second places in such a way that the burning front shape of the traveling nuclear fission wave along the second measurement is determined in accordance with the selected set of dimensional restrictions.

2. The method according to claim 1, where several of the fuel subassemblies of nuclear fission are elongated along the second dimension.

3. The method according to claim 1, where the first measurement is almost orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

4. The method according to claim 1, where the first dimension and the second dimension are practically orthogonal to each other.

5. The method according to claim 1, where the first measurement includes a radial measurement and the second measurement includes an axial measurement.

6. The method according to claim 1, where the first measurement includes an axial measurement and the second measurement includes a radial measurement.

7. The method according to claim 1, where the first measurement includes an axial measurement and the second measurement includes a lateral measurement.

8. The method according to claim 1, where the first dimension includes a lateral dimension and the second dimension includes an axial dimension.

9. The method according to claim 1, where the first places include outward directed places and the second places include inwardly directed places.

10. The method according to claim 9, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

11. The method according to claim 9, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

12. The method according to claim 9, where the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [1c1 | ey} in the inwardly directed places is larger than k _{e [GC1Ee} in the outwardly directed places.

13. The method according to claim 1, where the first places include inwardly directed places and the second places include outwardly directed places.

14. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

15. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

16. The method according to item 13, where the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [Ges1 | e} in the inwardly directed places is larger than k _{e [Ges1 | e} in the outwardly directed places.

17. The method according to claim 1, where the first places and second places are on opposite sides of the reference value along the first measurement.

18. The method according to claim 1, where the first places and second places include at least one attribute, which is almost equal.

19. The method according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

- 31 024235

20. The method of claim 18, wherein the at least one attribute includes a neutron flux.

21. The method according to p, where at least one attribute includes reactivity.

22. The method according to claim 1, where the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the rotation of at least one of several selected multiple fuel subassemblies of nuclear fission.

23. The method according to claim 1, where the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes turning over at least one of the selected several fuel subassemblies of nuclear fission.

24. The method according to claim 1, where the selected set of dimensional restrictions includes a predetermined maximum distance along the second dimension.

25. The method according to claim 1, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

26. The method according A.25, where the criterion of the combustion front includes a neutron flux.

27. The method according to p, where the neutron flux is associated with at least one of the selected multiple fuel subassemblies of nuclear fission.

28. The method according A.25, where the criterion of the combustion front includes neutron fluence.

29. The method according to p, where the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

30. The method according A.25, where the criterion of the combustion front includes burnout.

31. The method according to clause 30, where the burnout is associated with at least one of the selected several fuel subassemblies of nuclear fission.

32. The method according A.25, where the criterion of the combustion front includes the location of the combustion front in at least one of the selected several fuel subassemblies of nuclear fission.

33. The method according to claim 1, where the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission radially along the first measurement from the corresponding first places to the corresponding second places.

34. The method according to claim 1, where the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places.

35. The method according to claim 1, where the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes the controlled movement of the selected multiple fuel sub-assemblies of nuclear fission axially along the first measurement from the corresponding first places to the corresponding second places.

36. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission is practically spherical.

37. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission practically corresponds to the selected continuously curved surface.

38. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

39. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission has almost η-fold axial symmetry relative to the second dimension.

40. The method according to claim 1, where the shape of the combustion front of the traveling wave of nuclear fission along the second dimension is asymmetric.

41. The method according to p, where the shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

42. The method according to claim 1, further comprising the step of initiating a combustion front of a traveling nuclear fission wave by several assemblies of a traveling nuclear fission wave igniter.

43. The method of claim 42, further comprising the step of: at least one of several assemblies of a nuclear fission traveling wave igniter being removed before the controlled movement of selected multiple nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places.

44. The method according to item 43, where the extraction of at least one of several assemblies igniter of the traveling wave of nuclear fission before the controlled movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places includes removing at least one of several assemblies ig 32 322323 of a traveling wave nite from second places before the controlled movement of the selected several nuclear fission fuel subassemblies along the first measurement from The appropriate respective first seats in the second space.

45. The method according to claim 1, further comprising the step of causing the traveling wave nuclear reactor to become subcritical before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to corresponding second places.

46. The method of claim 45, wherein causing the traveling wave nuclear reactor to become subcritical includes introducing neutron absorbing material into the reactor core.

47. The method according to item 45, further comprising the step of recovering criticality after controlled movement of selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

48. The method according to clause 47, where the restoration of criticality includes the removal of at least part of the neutron-absorbing material from the reactor core.

49. The method of claim 45, further comprising the step of stopping the traveling wave nuclear reactor before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to corresponding second places.

50. The method of claim 49, further comprising the step of restarting the traveling wave nuclear reactor after a controlled movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to corresponding second places.

51. A method for controlling a traveling-wave nuclear reactor, comprising the following stages: a stage in which, for the burning front of the nuclear fission wave propagating along the first and second dimensions, the desired shape of the burning front of the nuclear fission traveling wave along the second dimension is determined in several nuclear fission fuel assemblies in accordance with the selected set of dimensional restrictions; and a stage in which the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places is determined depending on the desired shape.

52. The method of claim 51, further comprising the step of determining the existing shape of the combustion front of the traveling wave of nuclear fission.

53. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places, depending on the desired shape, includes determining the movement of the selected multiple nuclear fission nuclear fuel subassemblies along the first measurement from the corresponding first places in the corresponding second places so as to establish the desired shape.

54. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places, depending on the desired shape, includes determining the movement of the selected multiple nuclear fission nuclear fuel subassemblies along the first measurement from the corresponding first places in the corresponding second places so as to maintain the desired shape.

55. The method of claim 51, further comprising the step of determining the time to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

56. The method of claim 51, further comprising the step of moving the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

57. The method of claim 51, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

58. The method of claim 51, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

59. The method of claim 51, wherein the first dimension and the second dimension are substantially orthogonal to each other.

60. The method of claim 51, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement.

61. The method of claim 51, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement.

62. The method of claim 51, wherein the first dimension includes an axial dimension and the second dimension includes a lateral dimension.

63. The method of claim 51, wherein the first measurement includes a lateral measurement and the second measurement includes an axial measurement.

- 33,024,235

64. The method according to § 51, where the first places include outward directed places and the second places include inwardly directed places.

65. The method according to claim 64, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

66. The method according to item 64, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

67. The method according to item 64, where the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [Ges1 | e} in the inwardly directed places is larger than k _{e [Ges1 | e} in the outwardly directed places.

68. The method of claim 51, wherein the first places include inwardly directed places and the second places include outwardly directed places.

69. The method according to p, where the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

70. The method according to p, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

71. The method of claim 68, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [1ess1 |} ,. _e in inwardly directed places is larger than k _{e [1es1 |} ,. _e in outward places.

72. The method according to § 51, where the first places and second places can be on opposite sides of the reference value along the first dimension.

73. The method according to § 51, where the first places and second places include at least one attribute, which is almost equal.

74. The method according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

75. The method according to p, where at least one attribute includes a neutron flux.

76. The method according to p, where at least one attribute includes reactivity.

77. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second locations includes determining the rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

78. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first places to the corresponding second locations includes determining the inversion of at least one of the selected multiple nuclear fission fuel subassemblies.

79. The method of claim 51, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

80. The method according to 51, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

81. The method according to p. 80, where the criterion of the combustion front includes a neutron flux.

82. The method of claim 81, wherein the neutron flux is associated with at least one of several selected nuclear fission fuel subassemblies.

83. The method of claim 80, wherein the burning front criterion comprises neutron fluence.

84. The method of claim 83, wherein the neutron fluence is coupled to at least one of several selected nuclear fission fuel subassemblies.

85. The method according to p. 80, where the criterion of the combustion front includes burnout.

86. The method according to p, where the burnout is associated with at least one of the selected multiple fuel subassemblies of nuclear fission.

87. The method according to p. 80, where the criterion of the combustion front includes the place of the combustion front in at least one of several selected nuclear fission fuel subassemblies.

88. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the respective first places to the second places includes determining the radial movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places places.

89. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the second places includes determining the spiral movement of the selected multiple nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places places.

90. The method of claim 51, wherein determining the movement of the selected multiple nuclear fission subassemblies along the first measurement from the corresponding first places to the corresponding second places includes determining an axial movement of the selected multiple nuclear fission fuel subassemblies.

91. The method according to 51, where the determination of the desired shape of the combustion front of the traveling wave of nuclear fission includes determining the practically spherical shape of the combustion front of the traveling wave of nuclear fission.

92. The method of claim 51, wherein determining a desired shape of a burning front of a traveling wave of nuclear fission along a second dimension includes determining the shape of a continuously curved surface of a burning front of a traveling wave of nuclear fission.

93. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

94. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost η-fold axial symmetry relative to the second dimension.

95. The method according to 51, where the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

96. The method according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

97. A system comprising, for a combustion front of a traveling nuclear fission wave propagating along the first and second measurements, first electrical circuits for determining the desired shape of the burning front of a nuclear fission traveling wave along the second dimension in several fuel subassemblies of nuclear fission in accordance with a selected set of dimensional restrictions; and second electrical circuits for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

98. The system of claim 97, wherein the second electrical circuits are also designed to determine the existing shape of the combustion front of a traveling wave of nuclear fission.

99. The system of claim 97, wherein the second electrical circuits are also designed to determine the movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the respective first locations to the corresponding second locations so as to establish the desired shape.

100. The system of claim 97, wherein the second electrical circuits are also for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations so as to maintain the desired shape.

101. The system of claim 97, wherein the second electrical circuits are also for determining the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations depending on the desired shape.

102. The system of claim 97, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

103. The system of claim 97, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

104. The system of claim 97, wherein the first dimension and the second dimension are substantially orthogonal to each other.

105. The system of claim 97, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement.

106. The system of claim 97, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement.

107. The system of claim 97, wherein the first dimension includes an axial dimension and the second dimension includes a lateral dimension.

108. The system of claim 97, wherein the first dimension includes a lateral dimension and the second dimension includes an axial dimension.

109. The system of claim 97, wherein the first places include outwardly directed places and the second places include inwardly directed places.

110. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

111. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on a neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

112. The system of claim 109, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that there are more inwardly directed places than outwardly directed places.

113. The system of claim 97, wherein the first places include inwardly directed places and second

- 35,024,235 places include outward places.

114. The system of claim 113, wherein the inwardly directed and the outwardly oriented places are based on the geometric proximity to the central part of the reactor core.

115. The system of claim 113, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

116. The system of claim 113, wherein the inwardly directed and outwardly directed places are based on reactivity such that ^ _{£ &(; ίιν (} inwardly directed places are larger than ^ _{£ &(; ίιν (} outwardly directed places).

117. The system of claim 97, wherein the first places and second places are on opposite sides of the reference value along the first dimension.

118. The system of claim 97, wherein the first places and second places include at least one attribute that is substantially equal.

119. The system of claim 118, wherein the at least one attribute includes a geometric proximity to the central region of the reactor core.

120. The system of claim 118, wherein the at least one attribute includes a neutron flux.

121. The system of claim 118, wherein the at least one attribute includes reactivity.

122. The system of claim 97, wherein the second electrical circuits are also designed to determine the rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

123. The system of claim 97, wherein the second electrical circuits are also designed to determine the inversion of at least one of the selected multiple nuclear fission fuel subassemblies.

124. The system of claim 97, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

125. The system of claim 97, wherein the selected set of dimensional constraints is a function of at least one criterion of the combustion front.

126. The system according to p, where the criterion of the combustion front includes a neutron flux.

127. The system of claim 126, wherein the neutron flux is associated with at least one of several selected nuclear fission fuel subassemblies.

128. The system of claim 125, wherein the criterion of the combustion front includes neutron fluence.

129. The system of claim 128, wherein the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

130. The system according to p, where the criterion of the combustion front includes burnout.

131. The system of claim 130, wherein the burnup is associated with at least one of a selected multiple nuclear fission fuel subassemblies.

132. The system according to p. 125, where the criterion of the combustion front includes the place of the combustion front in at least one of several selected nuclear fission fuel subassemblies.

133. The system of claim 97, wherein the second electrical circuits are also intended for determining the radial movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

134. The system of claim 97, wherein the second electrical circuits are also designed to determine the spiral movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

135. The system of claim 97, wherein the second electrical circuits are also for determining axial displacement of selected multiple nuclear fission fuel subassemblies.

136. The system according to p. 97, where the first electrical circuits are designed to determine the almost spherical shape of the combustion front of the traveling wave of nuclear fission.

137. The system of claim 97, wherein the first electrical circuits are also designed to determine the shape of a continuously curved surface of the combustion front of a traveling nuclear fission wave.

138. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

139. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission has practically η-fold axial symmetry with respect to the second dimension.

140. The system of claim 97, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

141. The system of claim 140, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

142. A computer program product containing a first control program on a computer-readable medium designed to determine, for the front of burning of a traveling nuclear fission wave propagating along the first and second measurements, the desired shape of the burning front of a traveling nuclear fission wave along the second dimension in several nuclear fuel subassemblies divisions according to the selected

- 36,024,235 by a set of dimensional restrictions; and a second control program on a computer-readable medium, designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

143. The computer program product according to paragraph 142, where the second control program on a computer-readable medium is also intended to determine the existing shape of the combustion front of a traveling wave of nuclear fission.

144. The computer program product according to p, where the second control program on a computer-readable medium is designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape.

145. The computer program product according to p, where the second control program on a computer-readable medium is designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

146. The computer program product according to p, where the second control program on a computer-readable medium is also used to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

147. The computer program product according to p, where several of the fuel subassemblies of nuclear fission are elongated along the second dimension.

148. The computer program product according to p, where the first measurement is practically orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

149. The computer program product according to p, where the first dimension and the second dimension are almost orthogonal to each other.

150. The computer program product of claim 142, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement.

151. The computer program product of claim 142, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement.

152. The computer program product of claim 142, wherein the first measurement includes an axial measurement and the second measurement includes a lateral measurement.

153. The computer program product of claim 142, wherein the first measurement includes a lateral measurement and the second measurement includes an axial measurement.

154. The computer program product of claim 142, wherein the first places include outwardly directed places and the second places include inwardly directed places.

155. The computer program product of claim 154, wherein the inwardly directed and the outwardly oriented places are based on the geometric proximity to the central part of the reactor core.

156. The computer program product of claim 154, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

157. The computer program product of claim 154, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [£ e1 | ee} in the inwardly directed places is larger than k _e [| _es1 |> - _e in outwardly directed places.

158. The computer program product of claim 142, wherein the first places include inwardly oriented places and the second places include outwardly oriented places.

159. The computer program product of claim 158, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

160. The computer program product of claim 158, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

161. The computer program product of claim 158, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [£ e1 | ye} in the inwardly directed places is greater than k _e [| _es1 |> - _e in outwardly directed places.

162. The computer program product according to p, where the first places and second places can be located on opposite sides of the reference value along the first measurement.

163. The computer program product according to p, where the first places and second places include at least one attribute, which is almost equal.

164. The computer program product according to p, where at least one attribute includes a geometric proximity to the Central region of the reactor core.

165. The computer program product according to p, where at least one attribute includes a neutron flux.

- 37 024235

166. The computer program product according to p, where at least one attribute includes reactivity.

167. The computer program product according to p, where the second circuitry is designed to determine the rotation of at least one of the selected multiple fuel subassemblies of nuclear fission.

168. The computer program product according to p, where the second circuitry is designed to determine the inversion of at least one of the selected multiple fuel subassemblies of nuclear fission.

169. The computer program product of claim 142, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

170. The computer program product according to p, where the selected set of dimensional restrictions is a function of at least one criterion of the combustion front.

171. The computer software product according p, where the criterion of the combustion front includes a neutron flux.

172. The computer program product according to Claim 171, wherein the neutron flux is associated with at least one of several selected nuclear fission fuel subassemblies.

173. The computer software product of claim 170, wherein the burning front criterion includes neutron fluence.

174. The computer program product according to Claim 173, wherein the neutron fluence is coupled to at least one of several selected nuclear fission fuel subassemblies.

175. The computer program product of claim 170, wherein the criterion of a combustion front includes burn-out.

176. The computer program product according to Claim 175, wherein the burnout is associated with at least one of several selected nuclear fission fuel subassemblies.

177. The computer program product according to p, where the criterion of the combustion front includes the location of the combustion front in at least one of the selected multiple fuel subassemblies of nuclear fission.

178. The computer program product according to p, where the second control program on a computer-readable medium includes a third control program on a computer-readable medium, designed to determine the radial movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

179. The computer program product according to p, where the second control program on a computer-readable medium includes a fourth control program on a computer-readable medium, designed to determine the spiral movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

180. The computer program product according to p, where the second control program on a computer-readable medium includes a fifth control program on a computer-readable medium, designed to determine the axial movement of the selected multiple nuclear fission fuel subassemblies.

181. The computer program product according to p, where the first control program on a computer-readable medium includes a seventh control program on a computer-readable medium, designed to determine the almost spherical shape of the combustion front of a traveling nuclear fission wave.

182. The computer program product according to p, where the first control program on a computer-readable medium includes an eighth control program on a computer-readable medium, designed to determine the shape of a continuously curved surface of the combustion front of a traveling nuclear fission wave.

183. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

184. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost η-fold axial symmetry relative to the second dimension.

185. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

186. The computer program product according to p, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

187. A system comprising, for a burning front of a nuclear fission traveling wave propagating along the first and second measurements, first electrical circuits for determining the desired shape of the burning front of a nuclear fission traveling wave along the second dimension in several fuel subassemblies of nuclear fission in accordance with a selected set of times - 38,024,235 dimensional restrictions; second electrical circuits designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape; and a subassembly designed to move selected multiple nuclear fission fuel subassemblies responsive to the second electrical circuits.

188. The system of claim 188, wherein the second electrical circuits are also designed to determine the existing shape of the combustion front of a traveling nuclear fission wave.

189. The system of claim 188, wherein the second electrical circuits are also for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations so as to establish the desired shape.

190. The system of claim 188, wherein the second electrical circuits are also for determining the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first locations to the corresponding second locations so as to maintain the desired shape.

191. The system of claim 188, wherein the second electrical circuits are also used to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

192. The system of claim 188, wherein the multiple nuclear fission fuel subassemblies are elongated along the second dimension.

193. The system of claim 188, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

194. The system of claim 188, wherein the first dimension and the second dimension are substantially orthogonal to each other.

195. The system of claim 188, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement.

196. The system of claim 188, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement.

197. The system of claim 188, wherein the first dimension includes an axial dimension and the second dimension includes a lateral dimension.

198. The system of claim 188, wherein the first dimension includes a lateral dimension and the second dimension includes an axial dimension.

199. The system of claim 188, wherein the first places include outwardly directed places and the second places include inwardly directed places.

200. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

201. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

202. The system of claim 199, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that the _eGGes41ue in the inwardly directed places is larger than the _eGGes41ue in the outwardly directed places.

203. The system of claim 188, wherein the first places include inwardly directed places and the second places include outwardly directed places.

204. The system of claim 203, wherein the inwardly directed and the outwardly directed places are based on the geometric proximity to the central part of the reactor core.

205. The system of claim 203, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

206. The system of claim 203, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that there is more to the _eGGes41ue in the inwardly directed places than to the _eGGes41ue in the outwardly directed places.

207. The system of claim 187, wherein the first places and second places may be on opposite sides of the reference value along the first dimension.

208. The system of claim 188, wherein the first places and second places include at least one attribute that is substantially equal.

209. The system of claim 208, wherein the at least one attribute includes a geometric proximity to the central region of the reactor core.

210. The system of claim 208, wherein the at least one attribute includes a neutron flux.

211. The system of claim 208, wherein the at least one attribute includes reactivity.

212. The system of claim 188, wherein the second electrical circuits are also intended for determining rotation of at least one of the selected multiple nuclear fission fuel subassemblies.

213. The system of claim 188, wherein the second electrical circuits are also intended to determine the inversion of at least one of the selected multiple nuclear fission fuel subassemblies.

214. The system of claim 188, wherein the subassembly includes a nuclear fuel handling device.

215. The system of claim 188, wherein the subassembly is also intended for radial movement of selected multiple nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

216. The system of claim 188, wherein the subassembly is also intended for the helical movement of selected several nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

217. The system of claim 188, wherein the subassembly is also intended for axial movement of selected several nuclear fission fuel subassemblies.

218. The system of claim 188, wherein the subassembly is also intended to rotate selected several nuclear fission fuel subassemblies.

219. The system of claim 188, wherein the subassembly is also intended for inverting selected several nuclear fission fuel subassemblies.

220. A traveling wave nuclear reactor, comprising: a traveling wave nuclear reactor;

several fuel fission subassemblies of nuclear fission received in the active zone of a nuclear reactor on a traveling wave, each of several fuel fission subassemblies of nuclear fission intended to propagate in it the combustion front of a traveling nuclear fission wave along the first and second measurements;

first electrical circuits designed to determine the desired shape of the combustion front of a traveling wave of nuclear fission along the second dimension in several fuel subassemblies of nuclear fission in accordance with the selected set of dimensional restrictions;

second electrical circuits designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape; and a subassembly designed to move selected multiple nuclear fission fuel subassemblies responsive to the second electrical circuits.

221. The reactor according to claim 220, wherein the second electrical circuits are also designed to determine the existing shape of the combustion front of a traveling nuclear fission wave.

222. The reactor according to claim 220, wherein the second electrical circuits are also designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so as to establish the desired shape.

223. The reactor according to claim 220, wherein the second electrical circuits are also designed to determine the movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places so as to maintain the desired shape.

224. The reactor according to claim 220, wherein the second electrical circuits are also used to determine the time when to move the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places depending on the desired shape.

225. The reactor according to claim 220, wherein several of the nuclear fission fuel subassemblies are elongated along the second dimension.

226. The reactor according to claim 220, wherein the first measurement is substantially orthogonal to the elongated axis of several nuclear fission fuel subassemblies.

227. The reactor according to claim 220, wherein the first dimension and the second dimension are substantially orthogonal to each other.

228. The reactor according to claim 220, wherein the first measurement includes a radial measurement and the second measurement includes an axial measurement.

229. The reactor according to claim 220, wherein the first measurement includes an axial measurement and the second measurement includes a radial measurement.

230. The reactor of claim 220, wherein the first dimension includes an axial dimension and the second dimension includes a lateral dimension.

231. The reactor of claim 220, wherein the first measurement includes a lateral measurement and the second measurement includes an axial measurement.

232. The reactor of claim 220, wherein the first places include outwardly directed places and the second places include inwardly directed places.

233. The reactor according to p. 232, where directed inward places and outward places are based on

- 40 024235 of geometric proximity to the central part of the reactor core.

234. The reactor according to p. 232, where the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

235. The reactor according to claim 232, wherein the inwardly directed places and the outwardly directed places are based on reactivity such that k _{e [Gc1 | ee} in the inwardly directed places is larger than k _{e [1c1 |} ,, _e in outward places.

236. The reactor according to p. 220, where the first places include inwardly directed places and the second places include outwardly directed places.

237. The reactor according to claim 233, wherein the inwardly directed and outwardly directed places are based on the geometric proximity to the central part of the reactor core.

238. The reactor according to claim 233, wherein the inwardly directed places and the outwardly directed places are based on the neutron flux so that the neutron flux in the inwardly directed places is larger than the neutron flux in the outwardly directed places.

239. The reactor according to claim 233, wherein the inwardly directed and the outwardly directed places are based on reactivity such that k _{e [1es1 |} ,, _e in inwardly directed places is larger than k _{e [1es1 |} ,, _e in outward places.

240. The reactor according to claim 220, where the first places and second places can be on opposite sides of the reference value along the first measurement.

241. The reactor according to p, where the first places and second places include at least one attribute, which is almost equal.

242. The reactor according to claim 241, wherein the at least one attribute includes a geometric proximity to the central region of the reactor core.

243. The reactor according to claim 241, wherein the at least one attribute includes a neutron flux.

244. The reactor according to claim 241, wherein the at least one attribute includes reactivity.

245. The reactor according to p. 220, where the second electrical circuit is designed to determine the rotation of at least one of the selected several fuel subassemblies of nuclear fission.

246. The reactor according to p. 220, where the second electrical circuit is designed to determine the inversion of at least one of the selected several fuel subassemblies of nuclear fission.

247. The reactor according to claim 220, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.

248. The reactor according to claim 220, wherein the selected set of dimensional constraints is a function of at least one criterion of the combustion front.

249. The reactor according to paragraph 248, where the criterion of the combustion front includes a neutron flux.

250. The reactor according to p. 249, where the neutron flux is associated with at least one of the selected several fuel subassemblies of nuclear fission.

251. The reactor according to paragraph 248, where the criterion of the combustion front includes the neutron fluence.

252. The reactor according to claim 251, wherein the neutron fluence is associated with at least one of several selected nuclear fission fuel subassemblies.

253. The reactor according to paragraph 248, where the criterion of the combustion front includes burnout.

254. The reactor according to claim 253, wherein the burnup is associated with at least one of several selected nuclear fission fuel subassemblies.

255. The reactor according to paragraph 248, where the criterion of the combustion front includes the location of the combustion front in at least one of several selected fuel subassemblies of nuclear fission.

256. The reactor according to p. 220, where the second electrical circuit is designed to determine the radial movement of the selected multiple fuel subassemblies of nuclear fission along the first measurement from the corresponding first places to the corresponding second places.

257. The reactor according to claim 220, wherein the second electrical circuits are also intended for determining the helical movement of the selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places.

258. The reactor according to claim 220, wherein the second electrical circuits are also intended to determine the axial displacement of selected several nuclear fission fuel subassemblies.

259. The reactor according to claim 220, where the first electrical circuits are also designed to determine the almost spherical shape of the combustion front of a traveling wave of nuclear fission.

260. The reactor according to claim 220, wherein the first electrical circuits are also intended to determine the shape of the continuously curved surface of the combustion front of a traveling nuclear fission wave.

261. The reactor according to claim 220, where the desired shape of the combustion front of the traveling wave of nuclear fission is practically axisymmetric with respect to the second dimension.

262. The reactor according to p. 220, where the desired shape of the combustion front of the traveling wave of nuclear fission has almost η-fold axial symmetry relative to the second dimension.

263. The reactor according to claim 220, wherein the desired shape of the combustion front of the traveling wave of nuclear fission is asymmetric.

264. The reactor according to p. 263, where the desired shape of the combustion front of the traveling wave of nuclear fission is axisymmetric with respect to the second dimension.

265. The reactor according to claim 220, wherein the subassembly includes a nuclear fuel handling device.

266. The reactor according to claim 220, wherein the subassembly is also intended for radial movement of selected several nuclear fission fuel subassemblies from corresponding first places to corresponding second places.

267. The reactor according to claim 220, wherein the subassembly is also intended for the helical movement of selected several nuclear fission fuel subassemblies from the corresponding first places to the corresponding second places.

268. The reactor according to claim 220, wherein the subassembly is also intended for axial movement of selected several nuclear fission fuel subassemblies.

269. The reactor according to claim 220, wherein the subassembly is also intended for rotation of selected several nuclear fission fuel subassemblies.

270. The reactor according to claim 220, wherein the subassembly is also intended for inverting selected several nuclear fission fuel subassemblies.

271. A method of operating a traveling wave nuclear reactor, comprising the following step, in which at least one nuclear fission fuel assembly is moved outward from a first place in a running wave nuclear reactor to a second place in a traveling wave nuclear reactor.

272. The method according to p. 271, which also includes a stage in which at least one fuel assembly of nuclear fission is moved inward from the second place.

273. The method according to p. 271, where the first places and second places are based on the geometric proximity to the central part of the reactor core.

274. The method according to p. 271, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

275. The method according to p. 271, where the first places and second places are based on reactivity so that k _{e [1ec1 | ye} in the first places is more than k _{e [1ec1 |} ,. _e in second places.

276. A method of operating a nuclear reactor on a traveling wave, comprising the following stages: a stage in which determining the movement of at least one fuel assembly of nuclear fission in the first direction from the first place in the active zone of the nuclear reactor on the traveling wave to the second place in the active zone of the nuclear reactor on a traveling wave, and the second place is different from the first place; and a stage in which the movement of at least one fuel assembly of nuclear fission in the second direction from the second place is determined, the second direction being different from the first direction.

277. The method according to clause 276, where the first direction is directed outward and the second direction is directed inward.

278. The method according to clause 277, where the first places and second places are based on the geometric proximity to the Central part of the reactor core.

279. The method according to clause 277, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

280. The method according to p. 277, where the first places and second places are based on reactivity so that k _{e [1ec1 | ye} in the first places is more than k _{e [Ges1 | ye} in the second places.

281. The method according to clause 276, where the first direction is directed inward and the second direction is directed outward.

282. The method according to p. 281, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

283. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

284. The method according to p. 281, where the second places and first places are based on reactivity so that k _{e [1es1 |} ,. _e in second places more than k _{e [1ес1 |} ,. _e in the first places.

285. A method of operating a nuclear reactor on a traveling wave, comprising the following stages: a stage in which at least one fuel assembly of nuclear fission is moved in a first direction from a first place in the active zone of a nuclear reactor on a traveling wave to a second place in the active zone of a nuclear reactor a traveling wave, and the second place is different from the first place; and a stage in which the movement of at least one fuel assembly of nuclear fission in the second direction from the second place is determined, the second direction being different from the first direction.

286. The method according to p. 285, where the first direction is directed outward and the second direction is directed inward.

- 42 024235

287. The method according to p. 286, where the first places and second places are based on the geometric proximity to the Central part of the reactor core.

288. The method according to p. 286, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

289. The method according to p. 286, where the first places and second places are based on reactivity so that k _{e [1es1 |} ,. _e in the first places more than к _{е [1ес1 |} ,. _e in second places.

290. The method according to p. 285, where the first direction is directed inward and the second direction is directed outward.

291. The method according to p, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

292. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

293. The method according to p. 290, where the second places and the first places are based on reactivity so that k _{e £ £ £ £ £ у е} in second places is greater than k _{больше [1 1 | у в в} in the first place.

294. A method of operating a nuclear reactor on a traveling wave, comprising the following stages: a stage in which at least one fuel assembly of nuclear fission is moved in the first direction from the first place in the active zone of the nuclear reactor on the traveling wave to the second place in the active zone of the nuclear reactor a traveling wave, and the second place is different from the first place; and a stage in which at least one fuel assembly of nuclear fission is moved in the second direction from the second place, the second direction being different from the first direction.

295. The method according to p. 294, where the first direction is directed outward and the second direction is directed inward.

296. The method according to p. 295, where the first places and second places are based on the geometric proximity to the Central part of the reactor core.

297. The method according to p. 295, where the first places and second places are based on the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places.

298. The method according to p. 295, where the first places and second places are based on reactivity so that ke _{£ £ £ £ £ £ те} in the first places is greater than к _{е [1ес1 |} ,. _e in second places.

299. The method according to p. 294, where the first direction is directed inward and the second direction is directed outward.

300. The method according to p, where the second places and first places are based on the geometric proximity to the Central part of the reactor core.

301. The method according to p, where the second places and first places are based on the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places.

302. A method according to p.299, wherein the second space and the first place based on reactivity so that _EC1 to _e n _| , _{; e} in the second places is greater than к _{е [1ес1 |} ,. _e in the first places.

303. A method of operating a nuclear fission reactor, comprising the following stages: a stage in which a predetermined burnup level is selected; and the stage at which the movement of the selected several nuclear fission fuel assemblies in the core of the nuclear reactor is determined so as to achieve a burn-out level equal to a predetermined burn-out level in almost all nuclear fission fuel assemblies.

304. The method of claim 303, further comprising the step of moving the selected multiple nuclear fission fuel assemblies in the active zone of the nuclear fission reactor in accordance with a specific movement.

305. The method according to claim 304, further comprising the step of: determining the extraction of the respective selected multiple nuclear fission fuel assemblies when the burnup level is equalized to a predetermined burnup level.

306. The method according to p. 305, which also includes a stage in which the selected multiple fuel assemblies of nuclear fission are extracted in accordance with a specific extraction in accordance with a specific extraction.

Various aspects and embodiments are disclosed herein, however, other aspects and embodiments will be apparent to those skilled in the art. Various aspects and embodiments disclosed herein are for purposes of illustration and are not intended to limit the scope of the present invention, and the scope and spirit of the present invention are indicated by the following claims.

Claims (7)

CLAIM 1. A method for controlling the movement of fuel assemblies in a traveling nuclear reactor - 43 024235 wave to determine the shape of the burning front of a traveling wave, including the following stages: determine the existing shape of the burning front of a traveling wave; determine the desired shape of the burning front of the traveling wave, depending on the parameter associated with the burning front of the traveling wave; determine the amount of movement of at least one fuel assembly of nuclear fission in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor, the second place being different from the first place; and determine the amount of movement of at least one fuel assembly of nuclear fission in the second direction from the second place, and the second direction is different from the first direction. 2. A method for controlling the movement of fuel assemblies in a traveling wave nuclear reactor to establish the desired shape of the burning wave combustion front, comprising the following steps: determine the existing shape of the combustion front of the traveling wave; determine the desired shape of the burning front of the traveling wave, depending on the parameter associated with the burning front of the traveling wave; determine the amount of movement of at least one fuel assembly of nuclear fission in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor, the second place being different from the first place; moving said at least one nuclear fission fuel assembly in a first direction from said first place in a traveling wave nuclear reactor core to said second place in a traveling wave nuclear reactor; determine the amount of movement of at least one fuel assembly of nuclear fission in the second direction from the second place, and the second direction is different from the first direction; and moving said at least one nuclear fission fuel assembly in a second direction from said second location until said desired shape of a traveling wave burning front is established. 3. A method for controlling the movement of fuel assemblies in a traveling wave nuclear reactor to establish the desired shape of the burning wave combustion front, comprising the following steps: determine the existing shape of the combustion front of the traveling wave; determine the desired shape of the burning front of the traveling wave, depending on the parameter associated with the burning front of the traveling wave; determine the amount of movement of at least one fuel assembly of nuclear fission in the first direction from the first place in the active zone of the traveling wave nuclear reactor to the second place in the active zone of the traveling wave nuclear reactor, the second place being different from the first place; determine the time when to move the specified at least one fuel assembly of nuclear fission in the first direction from the specified first place to the specified second place, depending on the desired shape of the combustion front of the traveling wave; moving said at least one nuclear fission fuel assembly in a first direction from said first place in a traveling wave nuclear reactor core to said second place in a traveling wave nuclear reactor; determine the amount of movement of at least one fuel assembly of nuclear fission in the second direction from the second place, and the second direction is different from the first direction; and moving said at least one nuclear fission fuel assembly in a second direction from said second location until said desired shape of a traveling wave burning front is established. 4. The method according to any one of claims 1, 2 and 3, where the first direction is directed outward and the second direction is directed inward. 5. The method according to claim 4, where the first places and second places are based on at least one attribute selected from the geometrical proximity to the central part of the reactor core, the neutron flux so that the neutron flux in the first places is greater than the neutron flux in the second places and reactivity so that by the _e (1 _es41ue in the first place more than _e p _ec | _ | · .. <· in second place. 6. The method according to any one of claims 1, 2 and 3, where the first direction is directed inward and the second direction is directed outward. 7. The method according to claim 6, where the second places and first places are based on at least one attribute, - 44 024235 selected from the geometrical proximity to the central part of the reactor core, the neutron flux so that the neutron flux in the second places is greater than the neutron flux in the first places, and the reactivity so that ke | in the first places. FIG. 1A FIG. 1B - 45,024,235 FIG. 1C FIG. 1G) FIG. 1E - 46 024235 FIG. eleven - 47,024,235 FIG. 1Κ 26 P ² Controllable movement of selected from multiple nuclear fission fuel subassemblies radially along the first measurement from the corresponding first places to the corresponding second places FIG. 1Μ FIG. 1Ν - 48 024235 • γ FIG. 10 26 The controlled movement of selected from several nuclear fission fuel subassemblies axially along the first measurement from the corresponding first places to the corresponding second places + -48 FIG. 1P FIG. 10 - 49 024235 - 50 024235 FIG. 1Υ FIG. 1X (") At least one of several assemblies of a traveling nuclear fission wave igniter is removed before the controlled movement of selected from several fuel fission nuclear fission subassemblies along the first measurement from the corresponding first places to the corresponding second places FIG. 1Υ - 51 024235 At least one of several assemblies of the nuclear fission traveling wave igniter is removed from second places before the controlled movement of selected from several nuclear fission fuel assemblies along the first measurement from the corresponding first places to the corresponding second places' FIG. 1Ζ It is called that the traveling wave nuclear reactor becomes subcritical before the controlled movement of the selected several nuclear fission fuel subassemblies along the first measurement from the respective dog sites to the corresponding second places FIG. 1AA Criticality is restored after the controlled movement of selected several nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places FIG. 1AC - 52 024235 At least a portion of the neutron-absorbing material is removed from the reactor core FIG. 1AE u-66 Stop the traveling wave nuclear reactor before the controlled movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places FIG. 1AE A traveling-wave nuclear reactor is restarted after a controlled movement of selected several nuclear fission fuel subassemblies along a first measurement from respective first places to corresponding second places FIG. 1АР - 53 024235 FIG. 2A FIG. 2B 206 The movement of the selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places is determined so as to establish the desired shape 212 FIG. 2C 206 • 214 The movements of the selected several fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places are determined so as to maintain the desired shape FIG. 2Ώ - 54,024,235 FIG. 2E FIG. 2Р: 20 €> The rotation of at least one of the selected multiple nuclear fuel subassemblies is determined LRRRNIA 220 FIG. twenty 206 The turning over of at least one of several selected nuclear fission fuel subassemblies is determined FIG. 2H - 55 024235 206 Determine the radial movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places • 224 FIG. 2Ι 206 Determine the spiral movement of selected multiple nuclear fission fuel subassemblies along the first measurement from the corresponding first places to the corresponding second places • 226 FIG. 21 The axial displacement of several selected nuclear fission fuel subassemblies is determined FIG. 2K FIG. 2M - 56,024,235 FIG. 3A FIG. 3 v FIG. 3C FIG. 4A - 57 024235 FIG. 4B FIG. 4C FIG. 5 - 58 024235, - / -602 <START at At least one nuclear fission fuel assembly is moved outward from a first place in a traveling wave nuclear reactor to a second place in a traveling wave nuclear reactor -6O6 604 - 606 G stop V FIG. 6A FIG. 6B FIG. 7 - 59 024235 FIG. 8 900 / - \ D ⁹⁰² / start V At least one nuclear fission fuel assembly is moved in a first direction from a first place in a nuclear reactor in a traveling wave to a second a place in the active zone of a nuclear reactor on a traveling wave, and the second place is different from the first place Ιχ — 906 G1 at least one nuclear fission fuel assembly is moved in a second direction from a second place, the second direction being different from the first direction -. x-908 ζ - h x-908 / stop y FIG. nine FIG. 10A - 60,024,235 FIG. 10V FIG. 10C