EA040189B1 - SYSTEMS AND METHODS FOR LASER-ACTIVATED NEUTRON GENERATION FOR LIQUID PHASE-BASED TRANSMUTATION - Google Patents

Description

Field of invention

The subject matter of the invention described herein generally relates to systems and methods that facilitate the generation of energetic neutrons at a high rate by a laser-produced beam for the purpose of transmuting long-lived, high-level radioactive waste (transuranium and fission products) into short-lived radioactive nuclides or stable nuclides. , or rather, for subcritical liquid-phase transmutation of radioactive waste.

Background of the invention

Nuclear fission reactors generate a constant stream of spent fuel radionuclides: the US alone requires disposal of 90,000 metric tons [ref. 1], and by 2020 the world's spent nuclear fuel stocks will reach 200,000 metric tons, with an annual addition of 8,000 tons. In France, nuclear power accounts for 77% of all electricity, making the need for transmutation particularly acute. At present, there are no proper and adequate means available for handling these isotopic radioactive materials other than deep burial in the earth. The development of such means for the processing of isotopic radioactive materials requires the solution of two problems: first, the development of simple, reliable, safe and inexpensive ways to separate highly radioactive isotopes from other materials in order to avoid activation of non-radioactive material by transmutation; and, secondly, the development of a safe, inexpensive, energy efficient, universal method of transmutation.

Current approaches to radionuclide transmutation include drivers that support a subcritical fission reactor by external means: one based on an accelerator driven system (ADS) [ref. 2] and the other based on a tokamak driven system. system [link 3]. ADS systems use a high-energy (~1 GeV) beam of protons that is incident on a substrate (eg Pb, W) and knocks out neutrons (30+ neutrons per proton). These neutrons then support fission in a subcritical reactor. The tokamak-based system generates neutrons from deuterium-tritium reactions and uses these neutrons to power a subcritical reactor, also called a hybrid fission-fusion reactor.

There are also other approaches to nuclear waste transmutation based on subcritical operation, such as MOSART [ref. 4], as well as various approaches using generation IV reactors.

For these and other reasons, there is a need for improved systems, devices and methods to facilitate the generation of energetic neutrons at high speed through a laser generated beam for the purpose of subcritical liquid phase transmutation of radioactive waste.

The essence of the invention

The various embodiments presented herein generally relate to systems and methods for facilitating the transmutation of long-lived, high-level radioactive waste via fusion-generated neutrons into short-lived radioactive nuclides (radionuclides) or stable nuclides. Neutrons are generated by a fusion reaction between a deuterium beam and either tritium or deuterium targets, while the deuterium beam is laser accelerated by the main laser using a process known as coherent laser ion acceleration (CAIL) [ref. 6, RAST].

In exemplary embodiments, the transmutation process uses a subcritical operation using a compact device for transmuting radioactive isotopes (primarily lower actinide (HA) isotopes) performed in a tank containing a liquefied solution of a mixture of spent fuel waste components (such as fission products (FPs) and HA) dissolved in a solution of molten salts LiF-BeF ₂ (FLiBe) [reference 5]. The transmutation of NA is carried out with the help of energetic neutrons obtained as a result of a nuclear fusion reaction driven by a laser. Real-time monitoring and control of the FLiBe, NA and PD content in the transmutator is performed using active laser spectroscopy or a laser-driven gamma source.

In further exemplary embodiments, the target is formed from carbon nanotubes saturated with tritium.

In further exemplary embodiments, the deuterium or tritium targets are a laser-ionized gas with a density nearly equal to that of a solid. To form these targets, the prepulse laser (before the main laser) ionizes the target [Refs 7 and 8]. While the target remains solid, the CAIL-accelerated deuterons fusion (fuse) with tritium or deuterium.

In further exemplary embodiments, the transmutation reservoir is maintained in a subcritical state at all times. The subcritical mode puts a load on neutron sources, while energetic neutrons are produced in a closely coupled design:

- 1 040189 (1) by irradiating a nanometer foil consisting of diamond and deuteron, with the formation of a deuterium beam through the CAIL process;

(2) injection of accelerated deuterium into a nanometrically foamy tritium-saturated target synchronously and dynamically ionized by a prepulse laser.

Advantages of exemplary embodiments of laser-generated neutrons include:

a) the small size of the ion beams and their targets created by the laser;

b) fine control of neutrons: temporal as well as spatial. All fuel (NA) is within one neutron source fission mean free path;

c) high laser pulse repetition rate;

d) high efficiency of the laser from the socket, which is 30%.

In exemplary embodiments, the laser architecture as described in the previous paragraph is configured to provide pulses of, for example, <10 fs pulse energy of 10 mJ over a 20 µm spot size, resulting in an optimal a ₀ =0.5. The pump pulse for optical parametric chirped-pulse amplification (OPCPA) will be provided by a laser with a coherent amplification network (CAN), which allows for very high pump pulse repetition rates up to 100 kHz . The femtosecond pulses are produced by a femtosecond generator that delivers over a million pulses per second. After the generator, the pulses are captured at the desired frequency up to 100 kHz and then stretched to a few nanoseconds. After stretching, the pulse is amplified in the OPCPA cryogenic system to the level of tens of megajoules. The cryogenic OPCPA system preferably exhibits extremely high thermal conductivity, comparable to copper, which is necessary to remove the tens of kilowatts of thermal load generated during the optical parametric amplification process. With a spectral bandwidth corresponding to a pulse less than 10 fs, the pulse can be easily stretched to about one nanosecond and amplified by optical parametric amplification up to 10 mJ. In this process, the pulse is mixed with a pump pulse supplied by the CAN system with a duration of approximately ns and an energy >10 mJ. The amplified chirped pulse is then compressed back to its original value of <10 fs.

In the various embodiments provided herein, the low-level radioactive waste (LLRW) is transmuted in a liquid state, while the LLRW is dissolved in a lithium fluoride-beryllium fluoride (FLiBe) molten salt.

In the various embodiments provided herein, the transmutation plant operates in a subcritical mode, while a neutron source is required to drive the transmutation all the time.

In some exemplary embodiments, laser monitoring by laser spectroscopy is performed using a CAN laser [ref. 12].

In addition, a laser-driven source of gamma radiation (commonly referred to as laser Compton gamma radiation) is provided to monitor the content and behavior of HA and PD isotopes in tanks in real time.

An additional embodiment aims for a two-tank strategy to reduce the overall cost of neutrons, with one reservoir in critical mode and the other in subcritical mode. The two tanks contain two interconnected sets of tanks. The first tank or set of tanks preferably contains a mixture of Pu and lower actinides (HA), including neptunium, americium and curium (Np, Am, Cm), while the second tank or set of tanks contains only a mixture of lower actinides (HA). Since the first reservoir or set of reservoirs is in critical mode (Γ>φφ = 1), an external neutron source is not needed. In addition, the first tank or set of tanks is fueled using spent nuclear fuel (Pu and HA) after chemical removal of fission products. The first tank or tank set uses fast neutrons (fusion neutrons in addition to >1 MeV prompt fission neutrons) to transmute lower actinides (HA) and plutonium (Pu) while increasing curium (Cm) concentrations. Alternatively, a small amount of neutrons may be injected into the first tank or set of tanks to start burning Pu.

In a further embodiment, the walls of the first and second tank or set of tanks are made of carbon-based materials such as, for example, diamond. To protect the walls from chemical erosion and corrosion, the salt adjacent to the wall (facing the molten salt) is allowed to harden, preventing direct contact of the molten salt with the walls.

In a further embodiment, the transmutator embodiments described above may be applied in carbon dioxide recovery methods and processes, such as those involving its use as a coolant and the generation of synthetic fuel from it, to have

- 2 040189 fully negative carbon release. In the following exemplary embodiment, synthetic fuel (CH ₄ - methane) can be generated by the reaction CO ₂ + 4H ₂ -> CH ₄ + 2H ₂ O (Sabatier reaction), which requires 200-400 ° C and the presence of a catalyst, for example, Ni, Cu, Ru. CO ₂ can be extracted from the atmosphere, the ocean, or obtained by directly capturing CO2 at an emitter such as cars, buildings, chimneys or chimneys. The operating temperature range of the molten salt transmuter is 2501200°C, which makes it ideal for continuously providing the necessary temperature required for the Sabatier reaction to produce methane, and for providing an efficient way to stabilize and reduce atmospheric and oceanic CO2 concentrations.

Other systems, devices, methods, features, and advantages of the subject matter described herein will or will become apparent to those skilled in the art upon examination of the following figures and detailed description. All such additional systems, methods, features, and advantages are intended to be included herein, fall within the scope of the subject matter described herein, and are protected by the appended claims. In no event should the features of the exemplary embodiments be construed as limiting the appended claims unless those features are expressly stated in the claims.

Brief description of the figures

Details of the exemplary embodiments, including construction and operation, can be gleaned in part from a study of the accompanying figures, in which like reference numerals refer to like parts. The components in FIG. not necessarily drawn to scale; instead, emphasis is placed on illustrating the principles of disclosure. Moreover, all illustrations are intended to convey concepts, and relative sizes, shapes, and other detailed attributes may be illustrated schematically and not literally or accurately.

Fig. 1A illustrates a perspective view of an axially segmented transmuter vessel.

Fig. 1B illustrates a sectional view of an azimuthally segmented transmuter vessel.

Fig. 2A illustrates perspective views of a neutron source and a single adjacent tank, with neutrons generated from a deuterium-tritium (DT) fusion. The tritium is present as a gas, while the deuteron is created by laser-foil interaction inside the borehole. The wells are located at the entrance window.

Fig. 2B illustrates a single well assembly.

Fig. 3A illustrates perspective views of a neutron source and a single adjacent reservoir in the generation of neutrons from deuterium-tritium fusion. In this embodiment, the deuteron is generated by laser-foil interaction and the tritium forms a solid target on the back side of the well. Neutrons are produced when deuterons interact with tritium in a solid target. The wells are located in the reservoir of the neutron source.

Fig. 3B illustrates a single well assembly.

Fig. 4 illustrates a schematic representation of a laser accelerator system using a main laser and an ionization chamber with a prepulse laser to generate neutrons.

Fig. 5 illustrates a schematic representation of laser generation for a laser accelerator system.

Fig. 6 illustrates a side view of a liquid phase transmutation system with laser assisted separation and monitoring.

Fig. 7 illustrates a partial detail view of the central solution reservoir of the liquid phase transmutation system with laser separation and monitoring shown in FIG. 6.

Fig. 8 illustrates a side view of an alternative embodiment of a two-stage liquid phase separation and transmutation system with laser assisted separation and monitoring.

Fig. 9 illustrates an embodiment directed towards a two-tank strategy to reduce the overall cost of neutrons when tank 1 is in critical mode and tank 2 is in sub-critical mode.

Fig. 10 illustrates an embodiment directed to the process of generating synthetic fuels by chemical conversion of CO2, while the heat for the reaction is generated by fission.

Fig. 11 illustrates another embodiment directed to the process of generating synthetic fuels by chemical conversion of CO2, while the heat for the reaction is generated by fission.

Fig. 12 illustrates another embodiment directed to the process of generating synthetic fuels by chemical conversion of CO2, while the heat for the reaction is generated by fission.

- 3 040189

Fig. 13 illustrates another embodiment directed to the process of generating synthetic fuels by chemical conversion of CO2, while the heat for the reaction is generated by fission.

It should be noted that elements of similar structures or functions are generally represented by the same reference numerals for illustrative purposes throughout the figures. It should also be noted that the figures are only intended to facilitate the description of the preferred embodiments.

Detailed description

Each of the additional features and principles disclosed below may be used alone or in combination with other features and principles to provide systems and methods that facilitate the transmutation of long-lived radioactive waste into short-lived radioactive nuclides or stable nuclides using a powered neutron generation approach. nuclear fusion laser.

Moreover, various features of the specific examples and dependent claims can be combined in ways not specifically and explicitly listed to provide additional useful embodiments of the proposed principles. In addition, it should be clearly noted that all features disclosed in the description and/or claims are intended to be disclosed separately and independently of each other for the purposes of the original disclosure as well as for the purposes of limiting the claimed subject matter, regardless of the compositions of the features in the embodiments. and/or claims. It should also be expressly noted that all value ranges or integer group designations disclose every possible intermediate value or intermediate integer for purposes of initial disclosure as well as for purposes of limiting the claimed subject matter.

In exemplary embodiments, the transmutation process uses a subcritical operation using a compact device for transmuting radioactive isotopes (primarily lower actinide (HA) isotopes) performed in a tank containing a liquefied solution of a mixture of spent fuel waste components (such as fission products (FPs) and NA) dissolved in a solution of molten salts LiF-BeF2 (FLiBe). Such a process is described in US Provisional Application No. 62/544666 [ref. 5], which is incorporated herein by reference in its entirety. The transmutation of NA is carried out with the help of energetic neutrons obtained as a result of a nuclear fusion reaction driven by a laser. Real-time monitoring and control of the FLiBe, NA and PD content in the transmutator is performed using active laser spectroscopy or a laser-driven gamma source.

In the exemplary embodiments provided herein, neutrons are generated by laser-driven nuclear fusion to transmute long-lived radioactive nuclei into short-lived or non-radioactive nuclides.

In further exemplary embodiments, the deuterium or tritium targets are a laser-ionized gas with a density nearly equal to that of a solid. To form these targets, the prepulse laser (before the main laser) ionizes the target [Refs 7 and 8]. As long as the target remains at the density of a solid, deuterons accelerated by CAIL are fused (fused) with tritium or deuterium.

In further exemplary embodiments, the transmutation reservoir is maintained in a subcritical state at all times. Subcritical operation places stress on neutron sources, while energetic neutrons are produced in a tightly coupled design:

(1) by irradiating a nanometer foil composed of diamond and deuteron to form a deuterium beam through a process known as coherent laser ion acceleration (CAIL);

(2) by injection of accelerated deuterium into a nanometrically foamy tritium-saturated target, synchronously and dynamically ionized by a prepulse laser.

Referring to the drawings, in FIG. 1A and 1B show a segmented transmuter vessel 100. Fig. 1A shows a representative case of axial and radial segmentation of vessel 100 into three (3) vessel sections 100A, 100B and 100C. Fig. 1B shows a representative cross section of vessel 100 with radial and azimuth segmentation. The transmuter vessel 100 in the present embodiment is radially segmented into concentric cylindrical chambers or reservoirs 102, 104, 106, 108, and 110. The azimuthally segmented chamber 107 is a representative chamber used either for diagnostics or for an additional neutron source. By segmenting the vessel 100, the control and localization of various parameters can be improved more easily and/or more accurately, and the overall safety of the transmuter can also be improved by feedback from the various segments through the artificial neural network to the control valves to control the lower actinide concentration. This precise control optimizes the combustion of most of the lower actinides while remaining safe.

Tank or chamber 110 is a pressurized gas chamber composed of gaseous deuterium or tritium and functions as a source of neutrons to launch a self-sustaining

- 4 040189 chain reaction in the first and second concentric tanks 108 and 106. The first and second tanks

106 and 108 contain a mixture of molten FLiBe salt and lower actinides. The third concentric reservoir 104 contains fission products that are transmuted (transformed) into stable or short-lived nuclides. The fourth concentric reservoir 102 is a graphite reflector.

Fig. 2A shows a partial view of a single transmuter assembly 200 having a tank 212 and a neutron source tank 210 disposed therein. Tank 212 may be surrounded by additional tanks, as shown in FIG. 1A, 1B. In this embodiment, laser pulse 214 is projected onto mirror 220 and guided by mirror 220 to and into well 218. A plurality of individual laser pulses 214 and well chambers 218 are provided, such as thousands (1000) laser pulses and well chambers. An enlarged detailed view of a single chamber with wells 218 is shown in FIG. 2b. Well 218 is maintained under vacuum. The laser pulse 214 passes through the laser window 222 and irradiates the nanometer foil element 224. The nanometer foil element 224 is made of deuterated diamond and has a thickness of one or more nanometers, and preferably, a thickness of about 1-10 nm. A physical process known as coherent ion acceleration (CAIL) [see, for example, ref. 9 and ref. 24] accelerates deuteron and carbon ions from the nanometer foil element 224 in the form of a deuteron beam 216 towards the center of the reservoir 210 of the neutron source. The maximum energy attainable is given by equation 1.0 [see, for example, ref. 10; link 11]:

^max = (2α + l)Qmc ² (y/ajTl - 1) j ₀ where alpha usually = 3, mc ² = 0.511 MeV, ao~0.5 depending on other conditions. Therefore, for deuterium, the maximum energy is 0.41 MeV, and for carbon ions - 2.5 MeV. The deuteron beam 216 fuses with tritium in the neutron source reservoir 210, generating neutrons 226.

Fig. 3A and 3B show an alternative embodiment for neutron generation. The CAIL physical process is still used to accelerate deuterons in the form of deuteron beam 216, as discussed above with respect to FIG. 2A and 2B. As shown in FIG. 3A, a single transmuter assembly 200 includes a tank 212 and a neutron source tank 210 disposed therein. Tank 212 may be surrounded by additional tanks, as shown in FIG. 1A and 1B. In this embodiment, as in the previous embodiment, laser pulse 214 is projected onto mirror 220 and guided by mirror 220 to and into well 218. A plurality of individual laser pulses 214 and well chambers 218 are provided, such as thousands (1000) laser pulses and well chambers. An enlarged detailed view of a single chamber with wells 218 is shown in FIG. 3b. Well 218 is maintained under vacuum. The laser pulse 214 passes through the laser window 222 and irradiates the nanometer foil element 224. The nanometer foil element 224 is made of deuterated diamond and has a thickness of about one or more nanometers. The CAIL process accelerates deuteron and carbon ions from a 224 nanometer foil element into a deuteron beam 216 . Instead of being injected into the neutron source tank 210, deuteron beams 216 are injected onto a solid titanium-tritium target 228 at the rear end of well 218, resulting in the emission of neutrons 226. Wells 218 are located at the inlet window 211 into the neutron source tank 210 and also inside the tank 210 source of neutrons. The laser pulse 214 enters the well 218 through the entrance window 222 and interacts with the nanometer foil 224, creating a beam 216 of deuterons.

Fig. 4 illustrates in detail the laser-foil interaction in a single well 218 as shown in FIG. 2B and 3B. As shown, the laser pulse 214 has already passed through the entrance window 222 for laser radiation (see Fig. 2B and 3B). A laser pulse 214, such as, for example, from a CAN laser [Ref. 12], irradiates the nanometer foil 224, resulting in CAIL due to a ponderomotive force in a generally forward direction, in excess of the electrostatic pull force of the foil 224. Then a longitudinal electric field (not shown ) accelerates the deuteron and carbon beam 216 into the pressurized gas chamber 210 (see, for example, FIGS. 2A and 3A). Accelerated deuterium beam 216 collides with gaseous tritium and enters into a nuclear fusion reaction with it in chamber 210, thereby generating energetic neutrons 226, such as, for example, neutrons with energies of about 14 MeV. Neutrons 226 are released isotropically and fission of lower actinides occurs in reservoirs (see, for example, reservoirs 108 and 106, FIGS. 1A and 1B; reservoir 212, FIGS. 2A and 3A) surrounding the neutron source reservoir (see, for example, reservoir 110, Figures 1A and 1B, tank 210, Figures 2A and 3A).

In an alternative embodiment, the reservoir 210 of the neutron source consists of carbon nanotubes (CNTs) saturated with tritium. Pre-pulse lasers 230 and 232 irradiate reservoir 210 with laser energy penetrating into it in the above-threshold ionization mode, ionizing tritium-saturated CNTs [ref. 7; ref 8] and maintaining the ionized gas of carbon and tritium almost at the density of a solid for a short time in order for the deuteron beam to

- 5 040189 entered into a nuclear fusion reaction with ionized tritium plasma almost at the density of a solid. Lasers 230 and 232 are different from the main laser 214 used to accelerate deuterons. The pulse of the main laser (which accelerates the deuterons) and the prepulse lasers (for CNT + tritium ionization) must be synchronized so that the deuteron beam lags behind the prepulse and ionization occurs immediately before the deuteron beam. In this timing scheme, the prepulse lasers 230 fire before the prepulse lasers 232. This approach provides a highly efficient way to convert deuterium-tritium into fast neutrons. Approximate energy values for a prepulse ionization laser are estimated at 100–300 mJ for a CNT density of ¹⁰²² 1/ ^cm3 , a laser spot size of ^{10–7 cm2,} and an irradiated length of 100 cm.

In an alternative embodiment, one-cycle laser acceleration can also be used [Ref. 13; link 14].

In an alternative embodiment, the neutron source gas reservoir 210 of FIG. 2A has been replaced with gaseous deuterium.

In an alternative embodiment, the solid titanium tritium target 228 in FIG. 3B was replaced with a titanium-deuterium target.

In an alternative embodiment, the solid titanium-tritium target of FIG. 3B has been replaced by titanium. The deuteron beam 216 interacts with the solid titanium target 228 and is introduced into its lattice, subsequent deuterons in the beam 216 collide with the already introduced deuterons and enter into a nuclear fusion reaction with them to form neutrons 226.

In exemplary embodiments, the implementation of the design parameters of the laser, which are estimated from the prior art [reference 15], include intensity I=10 ¹⁷ W/cm ² ; laser wavelength = 1 µm; pulse duration = 5-10 fs; beam width = 5-10 µm. The laser is linearly polarized. Additionally, the foil thickness 224 (see FIGS. 2B, 3B, 4A, and 4B) is preferably obtained according to equation 2.0 d = A<2q [ dx 2.0

_{J n e} ^{( x ) _} _{_} ^_ W/cm ² , λ laser wavelength [reference 16].

In addition, in exemplary embodiments, the implementation of the design parameters of the accelerated deuteron beam are in the range of 30-200 keV. For this range, the frequency of Coulomb collisions is 10 times higher than the frequency of mergers. During one Coulomb collision, the deuteron loses on average 4% of its energy, i.e. energy is transferred to a target such as tritium. Therefore, the optimal deuteron energy is 200 keV, while we assumed 10 Coulomb collisions before the fusion occurs. The D-T fusion cross section is a maximum of 8 barn, at 60 keV.

A high-efficiency, high-frequency CAN laser [Ref. 12] is directed by an optics package, see for example, mirrors 220 (FIGS. 2A and 3A) onto a nanometer foil target 224 (FIGS. 2B, 3B, 4A, and 4B). The repetition rate of intense laser pulses is 100 kHz, issued with a high efficiency of 50%. Such a laser has previously been proposed as a diagnostic system [see, for example, reference 17]. For a supply of 10 ¹⁷ neutrons per second, a typical power of 200 kW is expected. This neutron flux is sufficient [see, for example, ref. 17] to power a 10 MW transmuter.

The efficiency of neutrons obtained under the action of a laser is shown in the table.

For the specified foil thickness and laser pulse length, the efficiency is shown for the conversion of laser energy into deuteron energy

Foil thickness [nm] Impulse [fs] Efficiency [%] 10 100 1.6 10 45 3.6 10 20 7.5 10 15 9.7 10 8 18 5 45 1 5 20 2.2 5 15 3.2 5 5 10 3.5 2 50

Fig. 5 illustrates the details of a laser system 500 for a transmuter. X-ray Coherent Enhancement Network (XCAN) 504 [ref. 12; ref 19] based on chirped gain

- 6 040189 Pulse (CPA) [ref 18] will provide high energy high pulse pumping for the OPCPA 506 [ref 20] The pulse will be generated by an XCAN laser, allowing very high pumping rates, up to 100 kHz. The femtosecond pulses are produced by a femtosecond generator 502, delivering over a million pulses per second. After the generator, the pulses are captured at the desired frequency up to 100 kHz before being stretched to a few nanoseconds. After stretching, the pulse is amplified in the OPCPA cryogenic system to the level of tens of megajoules. The amplified chirped pulse is then compressed back to its original value of <10 fs.

The cryogenic OPCPA system preferably exhibits extremely high thermal conductivity, comparable to copper, which is necessary to remove the tens of kilowatts of thermal load generated during the optical parametric amplification process. With a spectral bandwidth corresponding to a pulse less than 10 fs, the pulse can be easily stretched to about one nanosecond and amplified by optical parametric amplification up to 10 mJ. In this process, the pulse is mixed with a CAN-provided pump pulse of approximately ns duration and energy >10 mJ.

The transmutation laser combines four (4) laser technologies: CPA [ref 18], CAN [ref 12; ref 19], OPCPA [ref 20; link 21] and cryocooled nonlinear crystals [link 22]. As shown in FIG. 5, as an alternative, the CAN 504 can be replaced by a thin disk amplifier [reference 23]. The laser system for the transmuter is preferably capable of:

a) output a peak power corresponding to a ₀ =0.5, or an intensity of about 5*10 ¹⁷ W/cm ² with a spot size of, for example, 5 μm;

b) produce pulses, eg <10 fs, 10 mJ, with very high pulse rates in the range of 10-100 kHz, or with an average power that can reach 100 kW;

Additional features of the laser transmuter system include:

c) the OPCPA system is adapted for medium power. For more efficient cooling of a nonlinear crystal in order to increase its thermal conductivity, the crystal is installed on a cryogenically cooled heat sink. As mentioned earlier, at cryogenic temperature, the thermal conductivity of a crystal at or below liquid nitrogen temperature increases dramatically, reaching the thermal conductivity of copper [reference 22];

d) OPCPA system [ref. 20; ref 21] will enable 10 fs pulse generation. When pumping via CAN [ref. 12; reference 19], a coherent network amplifier can be used to amplify the initial pulse, for example, to a level of 10 mJ at 10-100 kHz;

e) for applications requiring, for example, 100 kW or more, N identical systems are configured in parallel. However, such applications do not require laser phasing;

f) As an alternative to the CAN system, amplifier pumping can be replaced by a thin disk laser system [Ref. 23].

Fig. 6 shows a laser operation system 600 for spectroscopy, active monitoring, and fission product separation. Component A is a CAN laser (respectively, in the form of beams); component B is a CAN laser modulator/controller (controlling laser properties such as power level, amplitude shape, periods and phases, relative operations, direction, etc.); component C are laser beams irradiating the solution and solvents in the central tank (see component K) for both monitoring and separation (or control of the chemical composition of solvents); component D is a solution that contains solvents, including ions of transuranic elements (such as Am, Cm, Np), which are subject to separation and transmutation using a transmutator E [reference 5] (releasing high-energy neutrons produced by nuclear fusion); component F is water, which stops neutrons from both the source of nuclear fusion, i.e. transmutator E, and from fission products; the G component is the sediment to be removed from the deposits at the bottom of the central tank (as an example of laser chemistry separation in the center tank containing the solution); component H is the unwanted precipitated elements that should not be transmuted at this time in this particular reservoir and should be transferred to another reservoir, where they will again be in a solution similar to this, subject to further separation and transmutation; component I is an artificial neural network (ANN) feedback loop and a computer that captures and monitors the tracked information signal, such as the fission product (FP) spectrum; component J is a detector of transmitted CAN laser signals (amplitudes, phases and frequencies, as well as deviations, etc.); the K component is the thin first wall of the central reservoir, which allows almost free passage of energetic neutrons generated by fusion or fission in the central reservoir, and the L component is an outer reservoir with a sufficiently thick wall that contains all materials and neutrons. Both the central tank K and the outer tank L are equipped with suitable monitors for temperature, pressure and some

- 7 040189 additional physical and chemical information in addition to CAN laser monitoring to monitor and alarm transmuter status, to keep tanks from going out of limits (e.g. runaway events) with suitable safeguards such as real time valves, electrical switches, etc. The Q component is a heat exchanger and the M component converts heat into electricity.

Once in service, the heated solution and water in the central and outer tanks K and L can be maintained in their condition by motors (or possibly suitable ducts within the tanks or their equivalents) as desired, and the excess heat removed and converted to electrical (or chemical) energy by the component M.

Referring to FIG. 8, in system 800, component P is a pipe (and its valve that controls flow between tanks) connecting the separated separator tank and transmuter tank. The O component represents the region of dissolution of the separated HAs introduced into the transmutator tank. Residual fission products remaining in the D component are removed through the pipe component R to the S component - a storage tank.

Referring to FIG. 7, in system 700, the central reservoir K contains a solution D of transuranic elements that have been recovered from the original spent fuel that has been liquefied with suitable solutions (such as acids). At this stage of the process, we assume that U and Pu have already been extracted from solution D by known methods (such as PUREX, i.e. extraction of uranium and plutonium by extraction). Thus solution D may include other elements such as fission products (PDs such as Cs, Sr, I, Zr, Tc, etc.). These elements may be prone to absorb neutrons, but not necessarily multiply neutrons, as the transuranium elements tend to be. Thus, PD needs to be removed from the solution D in the central tank K by chemical reactions and laser chemistry, etc. using CAN A laser and other chemical means. If these elements are deposited under the action of an added chemical and/or chemical excitation, etc. from the CAN laser, the deposited chemical components can be removed from this central tank K to another tank for processing elements such as fission products, etc.

Upon completion of the separation process, the transuranium elements (TEE, mainly Am, Cm, Np) are irradiated with neutrons from the transmutator E. These transuranium elements can have various isotopes, but all of them are radioactive isotopes, since they are behind uranium in their atomic number. Either neutrons from transmutator E or neutrons produced from the fission of transuranium elements will contribute to the transmutation of transuranium elements if the neutrons are absorbed by these nuclei.

Referring to FIG. 8, the transmuter and laser monitor and separator system 800 includes two separate tanks separating the separation and transmutation processes into two different tanks. For example, the separator (with attached laser monitor) is on the right, while the transmuter is on the left. The two systems are connected by a transfer pipe and valve, component P, which is used to transfer the precipitated (or separated) transuranium elements (TA) from the separator tank on the right to the transmuter tank on the left. The new carrier liquid (component O) preferably contains only (or contains mainly) HRE, but no longer the fission products that have been separated in the separator vessel on the right. Separation is performed either by conventional chemical means or by a laser (based on the CAN laser) which serves to excite (for example) the atomic electrons of the HA for chemical separation. The central tank D on the left contains mainly (or only) the HA solution. The elements left out of the liquid contain mainly DP, which are transported through a pipe (component R) to a storage tank (component S). Such PDs can be placed together in cured materials for subsequent disposal [Refs 22 and 23].

When fission occurs by neutron capture by transuranium elements, a high energy output (such as in the range of 200 MeV per fission) is typically expected from nuclear fission. On the other hand, the energy of nuclear fusion neutrons does not exceed 15 MeV. Both fusion neutrons and fission events in the central reservoir generate heat in the reservoir. The solution mixes this heat, as a rule, due to convection currents (either by itself or, if necessary, with the help of an externally driven engine). The carrier and extractor of the extracted heat, i.e. component M, removes the heat generated in the central reservoir and converts it into electrical energy. These processes need to be controlled both physically (e.g. temperature, pressure of the solution in the tank) and chemically (e.g. the chemical states of various molecules, atoms and ions in the solution through CAN laser monitoring) in real time for monitoring and feedback control purposes. according to the parameters of the tank by controlling valves and other controls, as well as the operation of the CAN.

A typical nuclear reactor produces the following spent fuel nuclear waste [refs 22 and 23] per 1 ton of uranium, which generates a power of 50 GW per day. During this operation, nuclear waste is: approximately 2.5 kg of transuranium elements (Np, Am, Cm) and approximately 50 kg of fission products. Quantity 2.5 kg of NA (lower actinides, i.e. transuranium elements)

- 8 040189 is approximately 100 mol, or approximately 6*10 ²⁵ HA atoms. This amount corresponds to approximately 7x10 ²⁰ HA atoms per second, approximately 10 ²¹ HA atoms per second. This translates into a laser power of approximately 1 kW if one photon (eV) is required to be absorbed by each HA atom to excite each atom by the laser. Let us take η as the efficiency of excitation of an ND atom by a single laser photon. Then the laser power P, absorbed by all HA atoms of the above amount per second, will be

P ~ (1/η) kW.

If η ~ 0.01, then P is approximately 100 kW. This number is not small. On the other hand, if one borrows efficient CAN laser technology with high flux density [Ref. 12], it will be within the reach of technologies. Under typical chemical exposures, we assume that the laser can either be close to continuous emission or have a very long pulse, so that the efficiency of the fiber laser and its flux density will be maximum. To maintain proper resonances or specific frequencies, the fiber laser's frequencies need to be tuned (most likely before use) to specific values.

As additional exemplary embodiments, the highly efficient neutron generation method is applicable to fields and processes requiring neutrons up to 14 MeV, such as, for example, medical applications in cancer treatment, such as, for example, boron neutron capture therapy (BNCT) and radioisotope generation. , structural integrity testing of buildings, bridges, etc., materials science and microchip testing, oil well logging, etc.

Two additional embodiments are presented: (1) a first embodiment aimed at a two-tank strategy to reduce the overall cost of neutrons when tank 1 is in critical mode and tank 2 is in sub-critical mode, and (2) a second embodiment is aimed at a more environmentally friendly a carbon negative transmuter through the production of synthetic fuels by chemical conversion of CO ₂ , while the heat for the reaction is generated by fission.

In the exemplary embodiment depicted in FIG. 9, transmuter 900 includes two interconnected sets of tanks, called tank 1 and tank 2. Tanks 1 and 2, which are essentially the same as the tanks shown in FIG. 2A and 3A may include a reservoir containing materials to be transmuted and a neutron source reservoir disposed therein, and as shown in FIG. 1A and 1B, these reservoirs may be surrounded by additional concentric reservoirs. Tank 1 preferably contains a mixture of Pu and lower actinides (HA), including neptunium, americium and curium (Np, Am, Cm), while tank 2 contains a mixture of only lower actinides (HA). Tank 1 is in critical mode (C = 1), which means that tank 1 does not require external neutrons. In addition, tank 1 is fueled using spent nuclear fuel (Pu and HA) after the chemical removal of fission products. Tank 1 uses fast neutrons (fusion neutrons in addition to >1 MeV prompt fission neutrons) to transmute lower actinides (HA) and plutonium (Pu) at elevated concentrations of curium (Cm). Alternatively, a small amount of neutrons can be injected into tank 1 to start burning Pu.

The lower actinides (HA) in tank 1, now with a higher concentration of curium (Cm), can be separated and fed into tank 2. The connected tank 2 works in parallel, burning lower actinides (HA) with an increased concentration of curium (Cm) in the subcritical ( Cl < 1) operating mode as described above. This process provides a safe and smooth way to burn all transuranic spent nuclear fuel (not just SA) while reducing the number of neutrons required for this by about 100 times.

In an additional embodiment, tank 1 and tank 2 are monitored in real time using a laser and gamma radiation. A broadband or scanning laser is used to monitor the elemental composition in tank 1 and tank 2 using laser-induced fluorescence and scattering. Gamma monitoring can be either active or passive. Passive gamma monitoring uses gamma radiation generated by nuclear decay or transition. Active gamma monitoring uses an external beam of gamma radiation with energies above a few MeV and is based on nuclear resonance fluorescence. Both active and passive monitoring provide information on the isotopic composition of the transmuter fuel. Information resulting from laser and gamma monitoring is collected and sent to a computer containing a logic block configured to predict and/or regulate future states of the transmuter by adjusting the replenishment of tank 1 with fuel or adjusting the concentration of HA in tank 2. To enable detailed For laser and gamma monitoring, the fuel in tank 1 and tank 2 is dissolved in a salt melt, which allows light to propagate. Real-time monitoring is an integral part of ensuring the overall active safety and efficiency of the transmuter, while detailed information about the composition of the transmuter will allow

- 9 040189 determine the position of the control rods, the replenishment of fuel and the extraction of fission products. Passive signs include a molten salt expanding with increasing temperature, causing the transmuter to shut down; the receiving reservoir is separated from the transmutator by a solidified plug, while any anomalous temperature spike will cause the plug to melt and the entire contents of the transmuter to flow out under gravity into the receiving reservoir, which is composed of neutron absorbers.

In another embodiment, the walls of tank 1 and tank 2 are made of carbon based materials such as diamond. To protect the walls from chemical erosion and corrosion, the salt adjacent to the wall (facing the molten salt) is allowed to solidify, preventing the molten salt from coming into direct contact with the walls.

In a further embodiment, the transmutator embodiments described above can be applied to carbon dioxide reduction methods and processes, such as those involving its use as a coolant and the generation of synthetic fuel from it, to have an entirely negative carbon release rate. In the following exemplary embodiment, synthetic fuel (CH ₄ - methane) can be generated by the reaction of CO ₂ + 4H ₂ -> CH ₄ + 2H ₂ O (Sabatier reaction), which requires 200-400 ° C and the presence of a catalyst, for example Ni , Cu, Ru. CO ₂ can be extracted from the atmosphere, the ocean, or obtained by directly capturing CO2 at an emitter such as cars, buildings, chimneys and chimneys. The operating temperature range of the molten salt transmuter is 250-1200°C, and therefore it is ideal for continuously providing the necessary temperature required for the Sabatier reaction to produce methane, and for providing an efficient way to stabilize and reduce CO2 concentrations in the atmosphere and ocean.

Referring to FIG. 10, a partial view of a synthetic fuel generation system 1000 is shown, including a transmutator vessel 1005, a secondary circuit piping 1001, a molten salt + HRE flow path 1002, a heat exchanger 1003, and a Sabatier reaction tank 1004. In this exemplary embodiment, the heat transfer medium in the heat exchanger tube is CO2, which is used directly in reservoir 1004. In the alternative embodiment shown in FIG. 11, the heat exchange tube of the heat exchanger 2003 of the synthetic fuel generation system 2000 is a closed and independent system, and the heat transfer medium can be replaced by molten salt. Synthetic fuel generation system 2000 is shown to include a transmutator vessel 2005, a secondary loop 2001, a molten salt + HRE flow path 2002, a heat exchanger 2003, and a Sabatier reaction tank 2004.

In a further alternative embodiment of FIG. 12 shows a partial view of a synthetic fuel generation system 3000 having a transmutator 3005, a heat exchanger 3001, a heat transfer medium flow path 3002, and a Sabatier reaction reservoir 3003. In this exemplary embodiment, the reactant CO2 from the Sabatier reaction is the heat transfer medium. In an alternative embodiment shown in FIG. 13, the heat exchanger circuit 4001 of the synthetic fuel generation system 4000 is shown as a closed and independent circuit with a heat transfer medium such as molten salt. A synthetic fuel generation system 4000 is shown including a transmutator 4005, a heat exchanger 4001, a heat transfer medium flow path 4002, and a Sabatier reaction reservoir 4003.

In a further embodiment, ionizing radiation generated within the transmutator and carried by the salt melt is used as an energy source of 1-10 eV to drive various chemical reactions. An energy source of 1-10 eV, for example, makes it possible to produce ammonia and convert CO ₂ + CH ₄ ^ CH3COOH.

The processing chain for use with embodiments of the present disclosure may include one or more computers, processors, microprocessors, controllers, and/or microcontrollers, each of which may be a discrete chip or distributed among (and part of) a number of different chips. The processing chain for use with embodiments of the present disclosure may include a digital signal processor (DSP), which may be embodied in hardware and/or software of the data processing chain for use with embodiments of the present disclosure. In some embodiments, the implementation of the DSP is a discrete semiconductor chip. A processing circuit for use with embodiments of the present disclosure may be communicatively coupled to other components as shown herein. The processing chain for use with embodiments of the present disclosure may execute stored software instructions that cause the processing chain to perform many different actions and adjust other components shown in the figures herein.

The processing chain for use with embodiments of the present disclosure may also execute other software and/or hardware algorithms. For example, a chain

- 10 040189 processing for use with embodiments of the present disclosure may interact with the communication circuit and perform analog-to-digital conversions, encoding and decoding, other digital signal processing, and other functions that help convert voice, video, and information signals to a format (for example, common-mode and quadrature) suitable for feeding into the communication circuit and can cause the communication circuit to transmit RF signals wirelessly over the communication channels.

A communication circuit for use with embodiments of the present disclosure may be embodied in one or more chips and/or components (e.g., a transmitter, receiver, transceiver, and/or other communication circuit) that perform wireless communication over communication channels according to a suitable protocol (e.g., , Wi-Fi, Bluetooth, Bluetooth Low Energy, Near Field Communication (NFC), Radio Frequency Identification (RFID), proprietary protocols, etc. One or more antennas can be included along with the communication circuit, as needed to function with different protocols and circuits.In some embodiments, the communication circuit for use with embodiments of the present disclosure may comprise an antenna for transmitting signals over communication channels.The processing circuit for use with embodiments of the present disclosure may also interact with the communication circuit to perform the inverse functions necessary to receive wireless P transmitting and converting it into digital data, voice and video. The RF communication chain may include a transmitter and receiver (eg, combined as a transceiver) and associated encoder logic. The reader may also include a communication circuit and interfaces for wired communication (eg, a USB port, etc.), as well as a circuit for determining the geographic location of the reader (eg, global positioning system (GPS) hardware).

The processing chain for use with embodiments of the present disclosure may also be configured to execute the operating system and any software applications that reside on the reader, process video and graphics, and perform other functions that are not related to processing transmitted and received messages. Any number of applications (also known as user interface applications) may be executed by the processing chain on a dedicated or mobile phone related reader at any time, and may include one or more applications associated with a diabetes monitoring mode, in addition to others commonly used. applications such as smartphone applications that are not associated with this mode, such as email, calendar, weather, sports, games, etc.

The memory for use with embodiments of the present disclosure may be shared by one or more different functional blocks present in the reader, or may be distributed across two or more of them (eg, as separate memory blocks present on different chips). The memory may also be a separate chip on its own. The memory may be non-temporal and may be volatile (eg, RAM or RAM, etc.) and/or non-volatile memory (eg, ROM or ROM, flash memory, FRAM, etc.).

Computer program instructions for performing operations in accordance with the described subject matter may be written in any combination of one or more programming languages, including an object-oriented programming language such as Java, JavaScript, Smalltalk, C++, C#, Transact-SQL, XML, PHP and the like, as well as traditional procedural programming languages such as the C programming language or similar programming languages. The software instructions may be fully executable on the user's computing device (eg, a reader) or partially on the user's computing device. The software instructions may reside partly on the user computing device and partly on the remote computing device, or entirely on the remote computing device or server, such as in cases where data of an identified frequency is downloaded to a remote device for processing. In the latter scenario, the remote computing device may be connected to the user computing device over any type of network, or may be connected to an external computer.

Various aspects of the present subject matter are set forth below, in an overview and/or in addition to the embodiments previously described herein, with emphasis on the relationship and interchangeability of the following embodiments. In other words, emphasis is placed on the fact that each feature of the embodiments may be combined with each and every other feature, unless explicitly stated otherwise or logically implausible.

According to embodiments, the transmutator system for transmuting long-lived radioactive transuranium waste comprises a neutron source reservoir, including a neutron source, where the neutron source contains a plurality of carbon nanotubes (CNTs) saturated with tritium, a plurality of prepulse lasers configured to irradiate the neutron source reservoir with penetrating into it laser energy in the above-threshold mode

- 11 040189 ionization to ionize CNTs and tritium and maintain the ionized gas of carbon and tritium at near solid density for a given period of time, a plurality of concentric tanks located around the neutron source tank and containing one or more mixtures of long-lived radioactive transuranium waste dissolved in salt FLiBe, a laser system oriented for axial propagation of a plurality of laser pulses into a neutron source, and a plurality of boreholes oriented for axial reception of said plurality of laser pulses, each of said plurality of boreholes including a foil element of a deuterated material, moreover, when the foil element is irradiated with a laser pulsed from said plurality of laser pulses, the foil element produces a plurality of deuteron ions, which are accelerated as an ion beam towards the center of the neutron source reservoir, where the deuteron beam undergoes a nuclear reaction nthesis with ionized tritium plasma almost at the density of a solid.

In embodiments, the foil element comprises a deuterated diamond-like material and said plurality of ions includes deuteron and carbon ions.

In embodiments, said plurality of ions are accelerated by coherent ion acceleration (CAIL).

In embodiments, the foil element has a thickness of one or more nanometers.

In embodiments, the laser pulse and pre-pulse lasers are synchronized so as to allow the deuteron beam to lag behind the tritium ionization.

In embodiments, said plurality of prepulse lasers includes a first set of prepulse lasers and a second set of prepulse lasers.

In embodiments, the first set of prepulse lasers is configured to fire before the second set of prepulse lasers.

In embodiments, the laser system includes a plurality of mirrors oriented to direct individual laser pulses from said plurality of laser pulses to and into individual wells of said plurality of wells.

In embodiments, said plurality of concentric reservoirs are segmented.

In embodiments, said plurality of concentric reservoirs are axially segmented.

In embodiments, said plurality of concentric reservoirs are azimuthally segmented.

In embodiments, said plurality of segmented reservoirs comprises a first concentric reservoir located around the neutron source and containing a first mixture of long-lived radioactive transuranium waste dissolved in the FLiBe salt, a second concentric reservoir located around the first concentric reservoir and containing a second mixture of long-lived radioactive transuranium waste dissolved in FLiBe salt, a third concentric tank located around the second concentric tank and containing a third mixture of long-lived radioactive transuranium waste dissolved in the FLiBe salt, and a fourth concentric tank located around the third concentric tank and containing one of water or water and a neutron reflecting screen.

In embodiments, the segmented first, second, third, and fourth concentric reservoirs are axially segmented.

In embodiments, the segmented first, second, third, and fourth concentric reservoirs are azimuthally segmented.

In embodiments, the laser system includes one of a CAN laser or thin wafer amplifier.

In embodiments, the laser system further includes an OPCPA system coupled to a CAN laser or thin wafer amplifier and a generator coupled to the OPCPA system.

In embodiments, the OPCPA is subjected to cryogenic cooling.

In embodiments, said plurality of concentric tanks form a first set of tanks, the transmutator system further comprising a second set of tanks containing a mixture of Pu and lower actinides (HA) including neptunium, americium, and curium (Np, Am, Cm).

In embodiments, the implementation of the second set of tanks is made with the ability to work in critical condition.

In embodiments, the walls of one of the first set of tanks or the second set of tanks are made from carbon-based materials.

In embodiments, the carbon-based materials are diamond.

It should be noted that all features, elements, components, functions, and steps described in connection with any embodiment provided herein are intended to be freely combinable and interchangeable with those taken from any other embodiment.

- 12 040189

If a particular feature, element, component, function, or step is described in relation to only one embodiment, then it should be understood that that feature, element, component, function, or step can be used with every other embodiment described here, unless not explicitly stated otherwise. Therefore, this paragraph serves as the foregoing basis and written basis for introducing into the claims, at any time, claims that combine features, elements, components, functions, and steps from various embodiments, or in which features, elements, components, functions, and steps from one embodiment are replaced by features, elements, components, functions, and steps from another embodiment, even though the following description does not expressly state in a particular case that such combinations or substitutions are possible. It is explicitly acknowledged that an explicit listing of all possible combinations and substitutions is unnecessarily burdensome, especially since the permissibility of each and all such combinations and substitutions can be readily recognized by those skilled in the art.

To the extent that the embodiments disclosed herein include or operate in conjunction with a memory, storage, and/or computer-readable medium, that memory, storage, and/or computer-readable medium is non-transitory. Therefore, to the extent that a memory, storage device, and/or computer-readable medium is covered by one or more of the claims, that memory, storage device, and/or computer-readable medium is only non-transitory.

Mention here and in the appended claims of an element in the singular does not exclude a plurality of such elements, unless the context clearly indicates otherwise.

While the embodiments are susceptible to various modifications and alternative forms, specific examples have been shown in the drawings and are described in detail herein. However, it should be understood that these embodiments are not limited to the specific form disclosed, but rather, these embodiments are to cover all modifications, equivalents, and alternatives falling within the spirit of the disclosure. In addition, any features, functions, steps, or elements of the embodiments may be listed in the claims or added to the claims, as well as negative features that characterize the scope of the claims with features, functions, steps, or elements that are not included in the claims. this volume.

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Claims (21)

CLAIM 1. A transmutator system for transmuting long lived radioactive transuranium waste, comprising a neutron source reservoir including a neutron source, the neutron source comprising a plurality of carbon nanotubes (CNTs) saturated with tritium; a plurality of prepulse lasers configured to irradiate the neutron source reservoir with laser energy penetrating it in an above-threshold ionization mode to ionize CNTs and tritium and maintain the ionized carbon and tritium gas at nearly solid density for a predetermined period of time; a plurality of concentric tanks located around the neutron source tank and containing one or more mixtures of long-lived radioactive transuranium waste dissolved in the FLiBe salt; a laser system oriented to axially propagate a plurality of laser pulses into the neutron source; and a plurality of boreholes oriented for axial reception of said plurality of laser pulses, wherein each of said plurality of boreholes includes a foil element of deuterated material, wherein when the foil element is irradiated with a laser pulse of said plurality of laser pulses, the foil element produces a plurality of deuteron ions accelerated in the form of a beam ions towards the center of the neutron source reservoir, where the deuteron beam enters into a nuclear fusion reaction with ionized tritium plasma at almost the density of a solid. 2. The transmutator system of claim 1, wherein the foil element comprises a deuterated diamond-like material and said plurality of ions includes deuteron and carbon ions. 3. The transmutator system of claims 1 and 2, wherein said plurality of ions are accelerated by coherent ion acceleration (CAIL). 4. Transmutator system according to claims 1 to 3, wherein the foil element has a thickness of one or more nanometers. 5. The transmutator system according to claims 1-4, wherein the pulse from the laser and the pre-pulse lasers are synchronized to ensure that the deuteron beam lags behind the ionization of tritium. 6. The transmutator system of claims 1 to 5, wherein said plurality of prepulse lasers includes a first set of prepulse lasers and a second set of prepulse lasers. 7. The transmutator system of claim 6, wherein the first set of prepulse lasers is configured to fire before the second set of prepulse lasers. 8. The transmutator system of claims 1 to 7, wherein the laser system includes a plurality of mirrors oriented to direct individual laser pulses of said plurality of laser pulses to and into individual wells of said plurality of wells. 9. Transmutator system according to claims 1 to 8, wherein said plurality of concentric reservoirs are segmented. 10. The transmutator system of claim 9, wherein said plurality of concentric reservoirs are axially segmented. - 15 040189 11. The transmutator system of claim 9, wherein said plurality of concentric reservoirs are azimuthally segmented. 12. The transmutator system according to claims 1 to 8, wherein said plurality of segmented tanks comprises a first concentric tank located around the neutron source and containing a first mixture of long-lived radioactive transuranium waste dissolved in the FLiBe salt; a second concentric reservoir located around the first concentric reservoir and containing a second mixture of long-lived radioactive transuranium waste dissolved in the FLiBe salt; a third concentric tank located around the second concentric tank and containing a third mixture of long-lived radioactive transuranium waste dissolved in salt FLiBe; and a fourth concentric reservoir located around the third concentric reservoir and containing one of water or water and a neutron reflecting screen. 13. The transmutator system of claim 12, wherein the segmented first, second, third and fourth concentric reservoirs are axially segmented. 14. The transmutator system of claim 12, wherein the segmented first, second, third, and fourth concentric reservoirs are azimuthally segmented. 15. The transmuter system of claims 1-14, wherein the laser system includes one of a CAN laser or a thin wafer amplifier. 16. The transmuter system of claim 15, wherein the laser system further includes an OPCPA system coupled to a CAN laser or thin wafer amplifier and an oscillator coupled to the OPCPA system. 17. The transmutator system of claim 16, wherein the OPCPA system is cryogenically cooled. 18. The transmutator system of claims 1 to 17, wherein said plurality of concentric tanks form a first set of tanks, the transmutator system further comprising a second set of tanks containing a mixture of Pu and lower actinides (HA) including neptunium, americium and curium (Np, Am, Cm). 19. The transmuter system of claim 18, wherein the second set of reservoirs is configured to operate in critical condition. 20. The transmutator system of claims 18 and 19, wherein the walls of one of the first set of tanks or the second set of tanks are made of carbon-based materials. 21. The transmutator system of claim 20, wherein the carbon-based materials are diamond.