BR102013033619A2 - isotopic transmutator fuser toroid cell - Google Patents

Abstract

isotopic transmutating fuser toroid cell. The present invention relates to an isotopic transmutation fuser (ctfti) toroidal cell characterized in that it is a compact nuclear fusion device; consisting of a plasma chamber (10), where it can be generated by means of an internal (176) or external (177) radio frequency antenna, a set of electrodes: plasma (13), suppressor (131), confinement (132), and target (11), which accelerated deuterium (d) or tritium (t) ions against a target containing metal hydrides (11), inducing dd, dt or tt reactions and generating neutrons; a cooling system and isolator (162) of the target; a neutron moderator (15) of dimension adjustable to the energetic level of the transmutation neutron beam; one or more sample positioning receptacles (161); neutron reflector (16), and shielding (160). ctfti is intended to transmute nuclides by absorbing neutrons, producing short- or long-lived radioisotopes rich in neutrons, radioactive materials and substances of interest in medical diagnosis and therapy, or fissile nuclides from fissionable nuclides; or transmute long half-life radionuclides into short or stable half-life radionuclides of interest in burning radioactive waste; or, in reducing the activity of unwanted radioactive sources

Description

The present invention relates to an Isotopic Transmuting Fuser Toroidal Cell (CTFTI), characterized in that it comprises a compact, toroidal activating nuclide device consisting of a plasma chamber (10) which can be powered by a radio frequency system (175) and in this case with internal (176) or external (177) antennas for ion excitation; a set of electrodes composed of plasma electrode (13), suppressor electrode (131), containment electrode (132?), and target electrode (11), which accelerated deuterium (d) or tritium (1 :) ions against the target consisting of metal hydrides deposited on the surface of the target electrode (11), where dd, dt or tt fusion reactions occur, generating neutrons; a cooling and target isolating system with coolant (162), a neutron moderator (15) of volume and dimension adjustable to the energy level of the transmutation neutron beam; one or more sample receptacles (161) to be transmuted; neutron reflector (16) and shielding (160). The purpose of CTFTI is to activate nuclides by neutron transmutation so that they can, for example, produce neutron-rich short or long-lived radioisotopes, producing radioactive substances and substances of interest in diagnosis and medical therapy; transmute long-lived radionuclides into short-lived or stable radionuclides of interest in burning radioactive waste or reducing activity from unwanted radioactive sources; or convert fissile nuclides from transmutation of fissionable nuclides.

Nowadays isotopic transmutation radioisotope production technologies occur, essentially, based on four processes: fission reactor (RT) fission neutron irradiation, producing neutron rich radioisotopes; irradiation of accelerated charged particles in Accelerators (AC), such as protons and alpha, generating proton-rich nuclides; Photon Transmutation (FT), emitted from sealed sources or electron interactions with heavy targets, like bremsstrahlung- reactions, and, by Radioisotope Generators (GR), through the decay of a parent parent nuclide ”In a“ child ”where the father was previously produced by the RT or AC processes. The RT, AC and GR processes require specific apparatus to produce transmutation.

Documents presenting devices proposing to produce radioisotopes by TF include: The patent application "Compact neutron generator for medical and commercial isotope production, fission product purification and controlled gamma reaction for direct power generatiori" - US20110268237A1 consists of a generator of neutrons, apparatus for producing radioisotopes and methods of commercial use and production of neutrons for medicine, which uses the reactions (γ, n) to produce neutrons by bombarding beryllium or deuterium with gamma photons. neutron, which are multiplied by a fission converter It is noted that due to the low neutron production of the reaction (γ, η), the fissile material must be incorporated into the device to amplify the neutron flux. neutron production set forth in US20110268237 differs significantly from this patent. Therefore, it proposes the production of neutrons by d-d, d-t or t-t fusion reactions and does not have a neutron amplifier. The document "Isotope generator" - US20070160176A1, proposes to produce radioisotopes by reaction (n, 2n) or (γ, η). The proponent suggests employing a neutron source that radiates a container adjacent to it, where samples are exposed to a neutron flux in order to generate isotopes. The reaction (n, 2n) occurs in this container and produces the radioisotopes of interest. A limitation of this patent is associated with the decrease in neutron flux due to the coupling of auxiliary systems consisting of heavy elements. The reaction in question requires high energy neutrons and is limited by the low probability of occurrence for most stable nuclides. After production, neutrons lose their energies by elastic collisions (n, n ') with light elements; or inelastic, preferably with intermediate atomic number elements, competing with any other type of nuclear reaction. The reactions (n, 2n) are sporadic compared to the reactions (n, n '). Thus, the neutron balance becomes precarious by the self-absorbing competition reactions on the device itself in reactions (n, n ') and (η, γ). In this case, the reactions (n, 2n) are known to produce neutron-poor and proton-rich radioisotopes, and hence positron emitters (β +). In addition, reactions (n, 2n) have a high energy threshold and low interaction shock sections (or probability of interaction) for most nuclides. In order to achieve significant shock section values, there is a remote possibility that tritium reactions could generate neutrons with energies of 14.1 MeV. In addition, it is expected that there is high neutron leakage from the compact device due to the high energy of emitted neutrons. Another relevant factor is the inherent moderation of the embedded materials, which reduces the energy of neutrons and thus hinders the occurrence of reactions (n, 2n). The use of tritium characterizes the device as radioactive in nature. Patent 20070160176 differs from the present technology in that it is based on reactions (n, 2n), which requires specific targets for this purpose, in addition to the other drawbacks mentioned.

The following are some patent documents associated with radioisotope production processes, AC, RT, GR.

Production from accelerated particle irradiation, AC: In "Device and method for producing radioisotopes" - US7940881, the authors propose to transmute isotopes from the irradiation of a fluid with a charged particle beam. Such patent is limited to the description of the target, its form and physical state. Note that the charged particle beams are generated by accelerators. particles such as cyclotrons, syncrocyclotrons or synchrotrons. The produced radionuclides are rich in protons and, in general, emitters β + or decay by electron capture.

Production from neutron irradiation (phesion), RT: In “Techniques for on-demand production of medical isotopes such as Μο-99 / Tc-99m and radioactive iodine isotopes including 1-131” - US20110280356, inventor proposes to radiate samples with neutrons from fission from uranium. In this case, fast fission neutrons are reflected and moderated by scattering, increasing the likelihood of further fission from 238U.

Uranium sandwich-shaped layers are used to maintain the rate of fission and neutron production. In this case, fission neutron production becomes the key to supplying radioisotope production.

Manufacturing from a pre-existing “parent” radionuclide that decays into another “child” radionuclide, process GR: In “Medical isotope generator systems” - US7554098, the inventors propose to use a 90Sr column to produce 90Y and separate it by means of an eluent solution. This is a typical patent that features a columnar radioisotope generator containing a pre-existing long half-life radionuclide that decays into a short half-life child radionuclide and can be eluted from the column. The parent radionuclide is produced by the methods described above, that is, in nuclear reactors or particle accelerators. These are chemically separated and confined in devices or capsules in which they will decay and produce the desired "child" nuclide. In this case, the “parent” nuclide, 90Sr, must be previously available, activated by other processes. The technical literature also presents patent documents with designs of neutron generating devices: In patent application US20130129027A1, "High flux neutronsource" of May 23, 2013, an apparatus for the production of thermal and epidermal neutrons is presented. positioned around a cylinder or spherical moderator to maximize neutron flux in a moderator-centered sample. In this context, the system is divided into a set of axial axis neutron generators placed in the radial direction of a cylindrical structure. Each unit produces neutrons directed to the center. The neutron fluxes generated from the multiple units are used for neutron activation analysis and ready range analysis for the elemental chemical concentration in a material. Thermal neutron absorption and inelastic scattering of fast epidermal neutrons in samples generate characteristic gamma rays that can be employed to identify the target element and its chemical concentration. A radiation detector is positioned above the apparatus axially to the sample cylinder, surrounded by neutron generating units. US2013 / 0129027 A1 differs from the present technology in that, due to its purpose of neutron activation analysis, the structures and dimensions employed are characteristics for this application, making it distinct. The multiple irradiation modules, placed radially to the axial sample cylinder, make the neutron management system distant and thus susceptible to neutron flux reduction leakage. The spectra and flows generated in the US2013 / 0129027 device are insufficient for the proposed radioisotope production. Consequently, the geometric parameters differ from the context proposed in this patent.- US7639770B2, entitled “Cylindrícal neutron generatof, presents a coaxially formed cylindrical neutron generator having a RF coaxial antenna plasma being produced, where in this plasma ions are generated. of deuterium. Neutron generation is coaxial to ion generator Cylinder length is long as needed. Neutrons are generated from the collision of ions with a tritium or deuterium target. This device is designed for neutron production for petroleum application, molecule analysis, airport explosives investigation and scanning purposes. Due to the lack of moderator, such device could not produce radioisotopes, because the neutrons produced are generated by the dd or dT reaction, which are 2.45 and 14.1 MeV, respectively, and in these energies the shock absorption sections of Neutrons for most nuclides are very low and no transmutation reactions occur. US2008 / 0089460A1, entitled “Proton Generator Apparatus for Isotope Production”, 2008, relates to improvements in electrostatic nuclear fusion reactors for neutron production, proton production and byproduct generation. It has a cylindrical configuration with a reactor-like polygonal internal structure that uses fusion reactions between hydrogen and its light-core isotopes. The system is elongated where there is a collision zone in which impacts directed to isotope production can be generated by proton reaction with appropriate nuclides. It is noted that the document addresses the production of radioisotopes through proton collisions. US2008 / 0039460 differs from the present technology in that it includes an electrostatic inertial confinement fusion reactor core. This technology is known in the fusion field and requires that plasma be produced and maintained in inertial confinement. In US2008 / 0089460, fusion reactions are generated by electrical pulses or particles that help heat the plasma. The resulting particles are neutrons and protons in dispersed and isotropic form. However, only protons can be accelerated inside the device. In this case, radioisotope production reactions can only occur in the collision of proton-poor ruclides, inducing the production of β + emitters. In this case, nuclear interactions are different from the proposed technology. In summary: US20080089460 discloses an inertial confined fusion reactor, with deflection and target orientations / interactions involving protons that collide with proton-poor nuclides; whereas in the present application the reactions and interactions are with neutrons in neutron poor nuclides. Thus, the geometry, functionality, process and technologies involved differ.

In Radioisotope Generators - GR, the decay of a “parent” nuclide into a “child” constitutes a natural transmutation, called radioactive decay; however, the parent nuclide must be produced by artificial means by the RT or AC methods. This type of generator is viable only when the “father” has a much longer half life than the “son”. A typical example of this technology is the commercial "Mo / 99mTc generator.

When transmuting into neutron rich nuclides, there is a need for a neutron generating source. Neutron production can be by fission reactors, RT. In fact, long-lived neutron-rich radionuclides have been produced by RT in Brazil: as 137Cs (30 years), 60Co (5 years), 131l (8 days). Others, rich in protons, generated by AC, such as 18F (2h), 201Ta (62.5h), 67Ga (78.3h) are found in Brazil, produced in commercial cyclotrons. Neutron production can also be established by sources. neutron-emitting sealed radioactive sources, for example, source of 252Cf which emits neutrons by spontaneous fission; and by d-d or d-t fusion reactions, for example, d-d or d-t neutron generators, initially designed for oil exploration research. One of the main advantages of these generators is based on the shock sections of the d-d, d-t and t-t reactions, which reach significant values at relatively low acceleration voltages (a few hundred kV). The essence of neutron generator technology is presented by Campos and Araújo (2010), (Araújo LW, Campos TPR “Issues on Beam-Plasma Instability -early Simulations Focusing on the Development of a Compact Neutron Generator”, Vol.32, July / September, 2010) and in more detail in Araújo LW's master's dissertation, entitled “Investigations in, Compact Neutron Generators” (UFMG / 2010). Transmutation is not only used to produce radionuclides. This technique can be used to convert long half-life radionuclides to short or stable half-life radionuclides. Signing is used to reduce the activity of radioactive waste or even unwanted liquid or sealed radioactive sources. In this case, the “burning” of radioactive waste produced in nuclear reactors may occur by inserting them in other reactors whose burning is produced during the process of fuel fission and electric power production. Another possibility is the chemical treatment and separation, applied in conjunction with the burning technique or not, where radionuclides are separated into classes according to their half life and activity. These are stored in ore-selected locations to be kept for millions of years to decay into a stable state. Nuclear fuel transmutation has also been researched involving high energy proton accelerators (1 GeV), which through scattering reactions (p, n) in lead and bismuth nuclei, among others, produce multiple neutrons, which are then used. in the conversion of radioactive waste. Transmutation of fissionable nuclides into fissiles, such as 232Th at 233U, can occur in heavy water (D20) nuclear reactors. Classic examples are CANDU-type heavy-water reactors, which in this case transmute 232U into 239Pu, in addition to 232Th in 233U, in addition to producing electricity. The process of Radioisotope Generators - GR is easy to use and low cost. There are several medical centers in Brazil that use 99Mo / 99mTC generators, distributed by the National Luclear Energy Commission - CNEN.

However, the country remains dependent on imports of 9% Mo irradiated on alumina-bound molybdenum substrate. Substrate activation is achieved in high-flux neutron reactors in Canada, the Netherlands, Argentina, Russia, Israel or the United States, specifically in the order of 1013 to 1014 n.cm‘2s'1. A recent worldwide crisis in the supply of this input, which occurred between 2009 and 2011, due to the shutdown of high-flow maintenance reactors has temporarily impaired or even paralyzed diagnostics made with 99mTc-labeled radiopharmaceuticals in nuclear medicine. In the Brazilian case, the government solution was to invest in a high flow reactor for the generation of Mo; however, it will take at least a decade to build and operate.

In the Photo-Transmutation - FT process, unstable gamma-emitting isotopes or those produced by accelerated electron braking radiation are high-emission sources of gamma radiation. Transmutation occurs by bombarding the target nuclei with gamma photons. Linear electron accelerators or even a large number of sealed high activity sources are required to supply gamma radiation for photo-transmutation. In TF, sealed sources consist of unstable isotopes that continuously emit radiation; Thus, logistical problems are associated due to the radiological protection associated with thousands of Ci (Curie) activity. This fact prevents the diffusion of this technology and, consequently, is not used in the commercial production of radioisotopes.

In the process of nuclear reactors - RT, large and complex industrial and energy installations are needed, in the order of billions of dollars, besides raising concerns in terms of radiological protection and management of radioactive waste, and it may also be possible to occurrence of severe nuclear accidents that cause damage to populations and the environment.

In the process of production by Accelerators - AC, most of the accelerators used in the production of radioisotopes have a cost of tens of millions of dollars. The radioisotopes produced by this process are rich in protons, decay by emitting β + or by the electronic capture method and have a short half life. There is also a need for transportation management from the production facility to the Iconsumidor center. For example, cyclotrons are facilities that produce β + emitting radioisotopes such as 18F, 11C, and 1SN. Such facilities are limited to proton-rich nuclides and it is impossible to produce neutron-rich β-emitting radionuclides. The class of emitting radionuclides β 'is produced solely with RT or FT. The production of radioisotopes by sealed sources or neutron generators has not been employed as a method of producing emitting radioisotopes (β '). The reason is that the intensity of neutrons produced by the d-d or d-t generator, isotropically, is in the order of 106 to 1011 n s-1 and is inversely proportional to the square of the target distance. Consequently, creep would reduce by a value around the fraction of 4Trd2, for example, relative to the 100 cm distance from the target, creep would reduce by a factor of the order of 7.95.10-6 cm. In turn, neutron energy emitted from dd or dt reactions in neutron generators is not suitable for radioisotope production, as the shock sections are very low, in the order of few millibarns (mb = 10-27 cm2) to large Therefore, due to the inadequate energy spectrum of emitted neutrons, low appearance and reduced intensity with the squared distance, the use of such technology for neutron transmutation for medical purposes has become unsuccessful. Thus arrangements using commercial radioisotope production devices are non-existent and impractical.

Sealed sources of 252Cf can achieve appearances in the order of 1012 n.s-1; however, they emit gamma radiation simultaneously with neutrons, the neutron energy spectrum is fission with maximum energies of 14.1 MeV, decay over time with a half-life of 2.7 years, neutron emission cannot be interrupted. need to be replaced periodically.

In the case of radioactive waste insertion in reactors, the possibility of nuclear accidents associated with chemical explosions make such technological processes unacceptable to our society. In Brazil, the treatment of tailings from the Angra I, II and future III plants is still an insoluble problem. Transmutation by spallation reactions involves high-energy proton accelerators (approximately GeV) coupled to nuclear reactors. Such facilities are high cost (billions of dollars) and are still experimental.

In the case of uranium thorium transmutation, pressurized water reactors (PWRs) cannot transmute fissionable elements into large-scale fissiles due to the low neutron economy. For each neutron absorbed in 235U (fuel I), 2.3 neutrons are emitted. Continuity of the chain reaction requires d 3 1 neutron and the rest escapes or is absorbed. This is because light water (H20) is a neutron absorber. Thus, there is a neutron deficit to transmute elements of interest into the reactor. Although Brazil has one of the largest reserves of 232Th in the world, its use has not yet occurred and is still useless to date. The transmutation of this element into a fissile element, in this case 233U, is of interest to the nation, due to the possibility of increasing the electrical production capacity by nuclear reactors.

Basically, the complexity, high cost, dimensions and radiological protection involved in the generation of radioisotopes by FT, RT and AC techniques limit the applications of radioisotopes. Neutron-rich radionuclides, especially short-lived radionuclides of less than 48 hours, for example, without limitation, are not produced. Obviously, the distance from production centers by any of the FT, RT and AC techniques precludes the use of short half-life radionuclides.

In addition, the elimination of radioactive waste in loci has not yet been resolved in Brazil. Such limitations can be circumvented by applying the in locus transmutation method through neutron activation generated by compact generators supported by fusion reactions. The main advantage is characterized by the shock sections of the d-d, d-t and t-t reactions, which reach significant values at relatively low acceleration voltages (few hundred kV) employed in the acceleration of these particles.

In order to overcome such existing limitations in both radioisotope production and related patents, the present invention is proposed to increase: (i) the supply of short-lived neutron-rich radioisotopes; ii) the independence of high flux reactor technology in the activation of Mo available only in few industrialized countries; iii) the production of short half-life radioisotopes in hospitals or clinics; iv) the possibility of transmutation of half-life radioisotopes. long in stable or short-lived radioisotopes, in locus, solving the problem of tailings produced in nuclear reactors, or undesirable sealed sources, v) the possibility of transmutation of fissionable elements into fissiles, allowing the use of Vi) reducing the cost of transmutation of radioisotopes vii) replacing complex technologies such as fission nuclear reactors and particle accelerators with simpler and more compact technologies viii) maintaining the philosophy of compact radioisotope generators , but not dependent on the pre-existence of a radioactive parent nuclide produced in fission reactors The particle accelerators or ix) the radiological safety of the installations; x) and allow the total shutdown of the installation and consequently interruption of the radiation produced in the device, similar to the X-ray equipment.

The present invention was then developed by the proposal of Toroidal Isotopic Transmuting Fuser Cell (CTFTI). CTFTI's proposal is to employ d-d, d-t, or t-t fusion neutron generation technologies and internal neutron moderation, reflection, and shielding systems to form a nuclear transmutation system. In this context, CTFTI is distinguished by its constitution of a unitary system, capable of ministering together the main electromagnetic and nuclear processes involved in nuclide transmutation. The system has compact dimensions, low cost compared to competing technologies, simplicity of development and operation, radiological safety with the possibility of complete radiation interruption and availability, and can operate continuously in radioisotope production at the radioisotope application site, consequently favoring the production and use of short-lived neutron-rich radionuclides. The present technology is compact, simpler (compared to nuclear reactors and particle accelerators), and capable of producing radioisotopes, or transmuting various isotopes or radioisotopes of interest, in their place of use, for example in hospitals, clinics, centers research, radioactive waste production sites, at a low cost.

Another relevant aspect regarding the production of radioisotopes provided by this technology is the ability of the present technology to switch on and off via radio frequency power and high electrical potentials, in the order of 200kV. Thus, upon shutdown, the device no longer produces radiation. Contrary to nuclear reactors, which do not cease radiation production, and adverse technologies that use neutron production from 252Cf sources, or photodisintegration reactions such as (γ, η); CTFTI becomes attractive because it does not produce radiation when turned off.

Another relevant aspect of the present technology is the comparison of radioisotope production by generators defined by GRs. In GRs there is a need for a radioactive precursor, called “parent”, produced in advance in nuclear reactors. The distribution of generators such as "Mo /" mTc are done weekly, and have an eluted activity, decreasing at the time of the father's half life, for example, of 67h of "Mo. The balance of activities between" Moe 99mTc is said to be transient. . In the technology presented, the CTFTI can continuously generate the “father”, whose internal activity in the device becomes constant, and consequently the balance between the “father” and “son” becomes secular. Parent production, therefore, ceases as soon as CTFTI is shut down. In addition, it is possible to make the radioisotope “son” available unlimitedly, without the need for periodic changes of GRs.

BRIEF DESCRIPTION OF THE DRAWINGS Figure 1 shows the isotode transmutation fuser toroid cell (CTFTI) and its main components. Figure 2 shows, in addition to the major components shown in Figure 1, an input and output cable holder and accessories (163). Figure 3 illustrates the geometry of the toroidal CTFTI, in perspective, where an entrance to the central receptacle (17) can be seen in the center of the cable and accessory bracket (163). Figure 4 illustrates some of the CTFTI structures in isolation. Figure 4a shows a view of the plasma chamber (10), the electrodes, (11) and (13), and the moderator (15). Figure 4b shows the electrode assembly (13) and (11), and the moderator (15). Figure 4c shows a view of the reflective closure structure (16) and the sample insertion and withdrawal opening (17) on the central axis of the CTFTI. Figure 5 illustrates the annular cylindrical shield structures (160), the upper reflector (16) and the upper cap (18) of the CTFTI. Figure 6 illustrates a semitransparent three-wire view of the toroidal CTFTI geometry identifying the central region of the sample insertion and withdrawal opening (17). Figure 7 illustrates the CTFTI identifying the insulating shield plate (165) from the electrodes and plasma chamber (10), cable and accessory support (163) and shield (160), and the shield plate ( 164) gamma radiation from the sample receptacles. Figure 8 illustrates the distribution of equipotential lines of the electric potential generated by the plasma electrodes (13) and the white electrode (11). Figure 9 illustrates the ion transport lines between the plasma electrode (13) and the target electrode (11) through the multiple openings on the plasma electrode (13), identifying the kinetic energy gain in the acceleration process through equipotential lines. Figure 10a illustrates a part of the cross section | CTFTI, detailing the electrodes. Figure 10b illustrates a total cross section of CTFTI as well as auxiliary systems. Figure 11 shows the normalized neutron spectrum at the periphery and center of the moderator.

DETAILED DESCRIPTION OF THE TECHNOLOGY The present technology is proposed by an Isotopic Transmuting Fuser Toroidal Cell (CTFTI) (Figure 1), filed in this patent application is a nuclide transmuting cell generated by neutron acceleration (d) or tritons (t) and collision on targets impregnated with d or t in dd (deuteron-deuteron), dt (deuteron-triton) or tt (triton-triton) fusion reactions. The CTFTI basically consists of the following components, arranged together: a toroidal geometry plasma chamber (10) that produces and provides deuterium ions, a set of electrodes, (11) (13), (131), and (132), specifically plasma electrode (13), suppressor electrode (131), focusing electrode (132) and target electroco (11), an ion acceleration environment characterized between plasma (13) and target electrodes ( 11), metal hydride deposited on the surface of the target electrode (11), an annular cylindrical region (162) separating the target electrode (11) from the moderator (15) containing a coolant and insulator (162), a cylindrical shell containing a neutron moderator (15), one or more sample receptacles (161), and in the form of external containment, a neutron reflector shell (16) and a radiation shielding shell (160).

More specifically, the CTFTI (Figure 1) comprises a device consisting of a plasma generator contained in a toroidal geometry plasma chamber (10) containing deuterium ionized gas with a 2 to 50 cm internal radius cylindrical cross-section. and longitudinal section with an average radius of 5 to 200 cm, having part of its cross-section limited by a cylindrical surface, with the radius ranging from 5 to 200 cm and length of 10 to 100 cm, composing the surface of the plasma electrode. (13) as a cylindrical segment, 0.1 to 1 cm thick, having from 1 to 100 spherical openings per square centimeter of radius ranging from 0.1 to 1 cm whose openings are oriented towards the target electrode ( 11) internal to the torus; may be followed by the suppression electrode (131) and the containment electrode (132); internal (176) or external (177) radio frequency antenna; a metal hydride target, incorporated with deuterium (d) or tritium (t), shaped like a cylindrical ring or toroidal section composing the target electrode (11), with an inner section radius of 2 to 50 cm, and length from 2 to 100 cm; thermal refrigerant and electrical insulator (162) circulating behind the target electrode (11); the neutron moderating material (15), confined between the electrical insulator (162) and the sample receptacles (161), in a solid cylindrical shape with a radius ranging from 5 to 200 cm and a length of 10 to 300 cm; wherein one or more sample receptacles (161) are of cylindrical shape with radius ranging from 2 to 5 cm and thickness from 0.1 to 1 cm and length from 3 to 300 cm; cable holder and accessories (163) covering the sample receptacles (161), protective plate (164), and externally the cell is confined by annular cylindrical reflective material (16); and by annular cylindrical shield (160) with upper cover (18) composed of reflective material (16) and shield (160), where sample insertion perforations (17) may be added; having reflector thicknesses or shielding of 10 to 50 cm, forming a cell limited by a cylindrical surface, of radius of 10 to 300 cm and length of 10 to 200 cm; this cell being composed of the target (11) and plasma (13) electrodes, and optional, consisting of metal parts, composing surfaces of copper, aluminum, titanium, or their alloy; being the target (11) represented by a metallic film deposited on the electrode of the target (11), composed of metal hydride being this target deuterized in a matrix of titanium, copper, gold, silver, tungsten; the moderator (15) consisting of low atomic neutron moderating material such as light water (H20), heavy water (D20), graphite, high density polymers, fluorinated polymers, polyethylene, teflon, beryllium, sulfur compounds, or mixtures thereof; the reflector (16) consisting of material consisting of chromium, copper, bismuth, lead, tungsten carbide or alloys or mixtures thereof; electrical insulators (165) consisting of electrical insulating material, which may cover the unexposed face of the target electrode, electrode joints and edges, and electrical connections (172) dd high voltage system (171) and radiofrequency connections and radio frequency system isolator (170) between these conductive materials and other parts of the device consisting of dielectric material such as glass, special ceramics and rubber; refrigerant (162) consisting of a thermal and electrical insulating coolant for the target (11), such as insulating mineral or organic oil; the shield (160) composed of polyethylene, water or graphite, mixed with neutron absorbing substances such as boron, lithium, cadmium or gadolinium compounds and coated with bismuth, lead or tungsten carbide; and valves (178) and the gas cylinder (179) that fills the plasma chamber (10) is neutral deuterium gas, or enriched with gaseous tritium. The moderator housing (15) and the sample receptacle (161) may be a single element so that the nuclides in flight can be inserted and combined in the moderator (15). The CTFTI can connect to a radio frequency (RF) system (175), with radio frequency connection and isolator (170), to a high voltage system (171) with high voltage (172) electrode power connections, a deuterium gas supply system (D2) (| l 78). The present device proposes a geometrically suitable structure, using suitable materials, capable of generating a neutron flux in a set of receptacles, capable of transmuting nuclides producing radioisotopes, among other applications. This neutron flux originates from the dd or dt nuclear reactions, and the deuterium ions generated in radiofrequency plasma are extracted from the toroidal chamber by an electrode, accelerated by the potential difference present between a set of electrodes, and taken to collide with a deuterized or tritiated hydride target, promoting nuclear reactions on the target. The toroidal shape aids in plasma retention (10), deuterium gas excitation and ionization, and lateral removal by it: plasma squeegee (13), towards the center of the torus, colliding with a concentric target (11) .

By isolating and cooling the high power electrode (11), the moderator (15) can be brought closer to it, allowing fast neutrons to lose their energies by elastic collisions and to achieve plausible kinetic energies to occur absorption and radioactive capture reactions. preferably in the thermal range, in sample receptacles. Thus, radioisotope generation processes such as GR, FT, AC and RT become outdated and unnecessary.

As for the main components of the CTFTI (present invention) as well as their functionalities, the CTFTI consists of: Plasma generator (10): represented by a plasma containment chamber fed by D2 gas (179), which can be generated by radiofrequency, and deuterium ion extractor through the plasma electrode (13). Radio frequency antennas are positioned internal (176) or external (177) to the plasma chamber (10), powered by a radio frequency power system (175) on the order of 0.5 to 5 KW at 13.5 MHz frequency. , which allows ionization of the gas of D2. RF systems 175, with antennas 176 or 177, the applied frequency and power for plasma generation, variations thereof, are part of plasma technology and are common knowledge and will not be described herein. patent.

Valve gas storage and distribution system (178) and cylinder (179): consisting of a pressurized deuterium (d2) cylinder (179), pressure control valves (178), which must be inside the chamber. (10) a pressure on the order of approximately 0.27 Pa, and pipes or hoses and connectors leading to feed into the plasma chamber, passing through the inlet and outlet cable support structure (163).

Electrode Set (13) and (10): Responsible for extracting and accelerating a beam of deuterium (d) or tritium (t) ions nuclei. An individual fixed voltage is applied to the electrodes, ranging from 30kV to -150kV, and the potential differential between electrodes can reach 180 to 200 kV. The electrodes are responsible for extracting, focusing and accelerating deuterium ions. These may include: plasma electrode (13), suppressor electrode (131), ground electrode lateral to suppressor (optional), focusing electrode (132 ) and the target-associated electrode (I0). The grounded, suppressor, and focuser electrodes are optional and will assist in orienting, suppressing electrons, and collimating the neutron beam against the target.

High voltage power system (171): 250 kV high voltage generator that supplies electrodes, cables and electrical insulators.

Plasma Generation System (175): In the case of plasma via RF, the system consists of a radio frequency generator, impedance matching network and power amplifier, which feeds the RF antenna, which must operate with power in order. kilowatts (from 0.1 to 5 kW) with 13.56 MHz frequency. For high powers it is necessary to include a cooling system in the plasma chamber and electrodes.

Refrigerated target (11): consisting of methybrid hydrides deposited on the target metal electrode plate (11), which produces dd (deuteron-deuteron), dt (deuteron-triton) or tt (triton-triton) fusion reactions, generating neutrons.

Cooling system (162): Heat exchanger and thermal refrigerant (162), consisting of insulating oil, which flows over the constituent metal of the target, enveloping it in order to absorb the thermal energy from the accelerated ion target. If the power is high, an external heat exchanger may be introduced to the CTFTI device, cooling the fluid contained therein to transfer heat to a secondary fluid such as water or air.

Moderator Receptacle (15): A receptacle, where there is an adjustable-sized neutron moderating material to enhance the energy spectrum of the neutron beam at the transmutation of interest, maximizing the rate of transmutation reaction.

Sample receptacle assembly (161): Place for introducing samples to be transmuted, disposed internally to the moderator; and / or the central axis of the CTFTI.

Neutron Reflector (16): A neutron reflection shell that minimizes neutron leakage or absorption to confine neutrons within the moderator.

Shield (160): External enclosure that limits radioactive exposure in the vicinity of the device during the period of operation.

Some materials that can be used in the constitution of the main components of the present invention include: Target (11) and Plasma (13) electrodes, and other optional - metal parts, forming surfaces, with cylinder-shaped perforations, trunk of a cone or sphere consisting of copper, aluminum, titanium, silver, gold, or metallic alloy, without limitation.

Target (11) - metallic film deposited on the target electrode (Π), composed of metal hydride, which may be titanium deuterium (TiDx), where x varies from 1 to 6; and metal hydrides may also be Ti , Ag, Au, Cu or W, these are deuterized or tritiated, without limitation.

Moderator (15): neutron moderating material, such as mild water (H20), heavy water (D20), graphite, high density polymers, fluorinated polymers, polyethylene, teflon, beryllium, sulfur compounds, or mixtures thereof, such as not limiting.

Electrical Isofator (165): Electrical insulating material, which can cover the unexposed face of the target electrode, electrode joints and edges, and electrode power connections (172), in between! These conductive materials and other parts of the device, consisting of dielectric material such as glass, special ceramics, rubber, without limitation.

Refrigerant (162): Target coolant (T), which also functions as an electrical insulator, commonly used in electrical transformers such as insulating mineral or organic oil, without limitation.

Reflector (16): material consisting of chromium, copper, bismuth, lead, tungsten carbide or alloys or mixtures thereof, without limitation.

Shield (160): Composed of polyethylene, water, or graphite, mixed with neutron absorbing substances, such as boron, lithium, cadmium or gadolinium, and coated with bismuth, lead, cadmium or tungsten carbide in a non-limiting manner. Gas that fills the plasma chamber (10): The feed gas contained in the plasma chamber (10) is neutral deuterium gas, or enriched with gaseous tritium. The CTFTI is shown in Figure 1, where the shield (160), reflector (16), the top cap (18), the toroidal plasma chamber (10), the target electrode (11), region of the insulating fluid can be identified. and refrigerant (162), moderator (15) and display receptacles (161). In CTET, there is the toroidal plasma chamber (10) (Figure 1). On the inner face of this torus there is a surface with multiple perforations, making up the plasma electrode (13) (Figure 3). The CTFTI (Figure 4) has an axial length along its central axis from 10 cm to 200 cm and a diameter of 10 to 300 cm with an external cylindrical appearance, containing: a toroidal plasma chamber (10), cross section circular radius ranging from 2 to 50 cm, and median radius of the longitudinal section from 5 to 300 cm. Figure 4a shows a view of the plasma chamber (10), the multi-aperture plasma electrode (13) connected to the plasma chamber (10), the toroidal section-shaped target electrode (11), the moderator ( 15), a cylindrical sample receptacle (161) and the volume to which the samples are inserted (17). Figure 4b also shows the plasma electrode (13) in isolation, followed by the target electrode (11), the moderator (15), the sample receptacle (161), and the sample positioning volume (17). There is also the target electrode (11), which takes a cylindrical shape (Figure 1). This can also take the form of a toroidal section (Figure 4). In the internal area of the cylinder represented by the target electroco (11) was a cylindrical annular section where the insulating fluid and refrigerant (162) is intentionally maintained (Figure 1). After this section there is a cylindrical volume containing the moderator (15) (Figure 4), where one or more cylindrical sample receptacles (161) are distributed containing the samples for transmutation.

Thus, the toroidal geometry of the plasma chamber is coupled to the plasma electrode (13) made of metal up to 05 mm thick with 1 to 100 cylindrical openings per square centimeter, each having a radius of 1 to 10 mm. mm, The plasma electrode is at an electric potential ranging from -200 to 0 kV, depending on the potential of the target electrode (11). Plasma chamber geometry is generated by the intersection of an inner cylinder with radius which is equal to the median radius of the torus minus 1 to 50% of the diameter of the inner section of the torus. The resulting face of this intersection produces a cylindrical segment of the plate electrode (13) (Figure 8).

After the plasma electrode (13) it is possible to insert an electron suppressor electrode (131), 2 to 10 cm from the outer face of the electrode (13). This electrode is optional, and assists electron removal from the beam. The potential applied to this electrode ranges from -100 to 100 kV, depending on the potentials applied to the target and plasma electrodes (Figure 10).

After the plasma electrode (13) there is the acceleration environment composed by the volume between the plasma electrode and the target electrode. These are 1 cm to 50 cm apart. It is possible to introduce containment electrodes (132) to converge the beam to the target (Figure 10). CTFTI has multiple functions. It can radiate different samples with different half-lives. For example, if used as a parent / child nuclide generator the child nuclide is eluted from an irradiated matrix made of the parent contained in columns, so the inlet / outlet is through a fluid that flows through ducts that circulate in internal column (sample receptacle), by means of elution ducts joining elution column (173) with elution vials (174), shown in Figure 10. If the cell is used to burn radioactive waste, these are positioned in the sample wells (161) and irradiated for a long time, the lid (18) of the device having to be gripped and large amounts of material to be irradiated. The closing structure, or lid (18), illustrates this possibility. If the cell is to produce short half-life nuclides (hours or minutes), small amounts of solid material must be inserted through the central opening (17), irradiated, and rapidly removed. Thus, there are three possibilities for sample input / output. In a CTFTI unit there is no need to have all three possibilities. Depending on their primary function, one or two possibilities are required.

Concentricly, there is the toroidal shaped target electrode (11) with defined geometry from a segment of a toroid with a circular section with an inner radius of 02 cm to 50 cm, obtained by cutting the toroidal volume by a radius cylinder. equal to the average radius plus 10 to 50% of the diameter of the circular section. The average radius of the toroid of the target electrode can assume values from 05 to 200 cm. The target electrode may also be cylindrical in shape, with a radius ranging from 05 to 200 cm and length from 04 to 100 cm. The target electrode is maintained at a potential ranging from 0 to 200 kV depending on the potential applied to the plasma electrode.

Following the target electrode, there is a concentric insulating surface 1 to 5 cm from the target electrode, maintaining the same geometry as the target, composing a region that receives the insulating fluid and refrigerant. This fluid cools the target and isolates the electrical potential of the target. The refrigerant may be circulating and then cooled in a heat exchanger external to the CTFTI, where the fluid exchanges heat through a coil with another fluid. The need for cooling depends on the power of the fusion generator. The surface defining the cooling region also defines the moderator receptacle (161). This can then be contained in a volume with a cylindrical or toroidal side surface. The radius of this geometry can range from 5 to 200 cm, and length from 5 to 100 cm. The radius and length define a volume, which must be adjusted to suit the process of moderating fast neutrons to the maximum rate of production of the radioisotope of interest to be transmuted, or until reaching the maximum neutron flux in the thermal or epidermal band in the center. of the sample receptacles. Thus, the moderator receptacle must be designed to achieve an optimal configuration.

Sample receptacles (161) consist of cylinders from 01 mm to 50 mm radius, and length ranging from 03 cm to a maximum length equivalent to the moderator receptacle length. The number of receptacles and their internal moderator positions may vary to benefit from the largest neutron flux region in the desired spectrum.

In CTFTI there is an annular cylindrical ring that makes up the outer shield (160) and an annular cylindrical ring of the reflector (16). The top cover also consists of a shield (160) and a reflector (16). Figure 1. All the elements described above are confined by the neutron reflection structure (16), with cylindrical caps 5 cm to 50 cm thick and radius 10 to 300 cm, with sides whose thickness varies from 5 to 50 cm . After the neutron reflection material (16) there is the lower, side (160), and upper (160) neutron and photon shields wrap around the previously discussed elements. The thickness of this shielding may vary from 5 to 50 cm. Toroidal CTFTI shield (160) and reflector (16) structures are essential in reducing neutron leakage (Figure 5).

CTFTI units may have openings (17) for direct introduction of samples into the receptacles, in diameter equivalent to the receptacle. The dimensions mentioned are not limiting. The cable and accessory bracket (163) consists of a cylindrical structure connected to the outer wall of the CTFTI (Figure 2). This cable holder (163) contains the column feed tubes present in the sample receptacles (161), the plasma chamber internal gas supply (10), and the refrigerant supply connected to the isolation and cooling region. (162), and high voltage electrical conductors supplying the target electrodes (11), as well as additional instrumentation for radiation detection. This holder is coated with a tungsten or lead plate, which shields the radiation ranges emitted by the radioactive samples. This additional shielding protects the operator if the CTFTI is required to open columns contained in the receptacles. Insertions of electrical pipes or hoses in the cable holder and fittings (163), connectors, conductors and cables for gas supply, insulators and electrical potential supply points, as well as cooling system, are simplified in Figure 2, by the cable support structure and accessories (163); being presented as a cylinder disposed on top of the sample receptacles (161), 1 to 5 cm thick, connected to the outside by a rectangular structure, where the conductors, ducts and electrical cables are passed internally.

In addition to tubes that feed the anthrust receptacle contained internally in the cable holder and fittings (163), there is the possibility of introducing samples directly through the central axis of the device (Figure 3). In this case there is an opening in the cable and accessory holder (163) (Figure 3). Thus, samples can be inserted and removed on the central axis of the device (17), being optional. The cell may transmute one or more long half-life radionuclides into the precursor of a short half-life radionuclide, which may be defined in the group: Mo-99 / Tc-99m, Sr-90 / Y-90, Rb-81 / Kr-81m, Hg-195 / Au-195m; W-188 / Re-188, Si-32 / P-32, without limitation. In this case the matrix with the precursor nuclide is enclosed within a column internal to the sample receptacle (162) and fine inlet and outlet plastic or polymeric tubes allow for liquid elution of the column from the outside of the toroidal cell. The column elution method is shown in Figure 10A. This illustrates a cross-sectional portion of the CTFTI showing the position of the radioisotope elution column (173), the eluent exit and entry (174), the confinement electrode (132), the suppression electrode (131), the plasma electrode (13), radio frequency connection and isolator (170), reflector (16) and shield (160).

Auxiliary systems are illustrated in Figure 10B in a cross section of CTFTI. Shown are the radio frequency power system (175), the high voltage system (171), the high voltage connections (172), the deuterium valve gas supply system (178), and the gas cylinder (179), and possible internal (176) or external (177) RF antennas and RF and isolator connections (170).

An electromagnetic simulation reproducing the neutron beams in the accelerating environment at CTFTI generated the electric potential lines between the plasma (13) and target (11) electrodes, where the moderator (16) and the plasma chamber ( 10) (Figure 8). All the reflector-coated structure (16) (Figure 8). The ion transport of neutrons between these potentials is presented in Figure 9, in a three-dimensional way. It can be observed that 180 keV kinetic energy deuterium beams are generated by multiple plasma electrode perforations (Figure 9). The CTFTI has the following components and dimensions, without limitation, externally composing a volume limited by a cylindrical surface, with a radius of 10 to 300 cm and length of 10 to 200 cm, and internally containing: a plasma chamber (10 ), in a semi-toroidal / cylindrical shape, with a cylindrical cross-section with an inner radius of 2 to 50 cm, and a longitudinal section with a median radius of 5 to 200 cm, having a cross-sectional portion with a cylindrical surface, with c radius ranging from 5 to 200 cm and length from 10 to 100 cm composing the surface of the plasma electrode (13) as a cylindrical segment, and thickness from 0.1 to 1 cm, having from 1 to 50 spherical openings per square centimeter of radius ranging from 0.1 to 1 cm, containing a target in the shape of a semi-toroidal or cylindrical segment (11), with an inner section radius of 2 to 50 cm, and a cylindrical case of a length of 2 to 100 cm; the moderator receptacle (15), cylindrical ndrico solid with a radius ranging from 5 to 200 cri and length of 10 to 300 cm containing moderator material (15); and internally to the moderator there are sample receptacles (161); in cylindrical shape with a radius ranging from 2 to 5 cm and a thickness of 0.1 to 1 cm and a length of 3 to 300 cm; all elements being confined by a reflection structure (16) covering the structure in cylindrical shape with lids of 10 to 50 cm thickness; and thereafter a shield covering (160) of thickness from 10 to 50 cm; may have openings (17) for sample introduction.

At the target electrode (11) nuclear reactions dd or dt occur as indicated in the expressions below: (1) (2) (3) Where d is the hydrogen isotope 2H, and t is the hydrogen isotope 3H, ep is the same as hydrogen (H1), Q represents the kinetic energy of the reaction products, where n is emitted with 2.45 MeV in reactions dd and 14.06 MeV parad-f.

Reactions 1 and 2 can occur on the target, ie d-d, which generate (d, n ') and (d, p). However, only reaction 2 has the byproduct of neutron emission. The shocks (probability of interaction) for reactions (d, n '), (d, p), (d, d), (t, n), obtained from database EftlDF / B-VI.8, The determination of the neutron yield, γ, of (£ TFTI) can be assessed by equation 1. (1) Where ηα is the number of neutrons per cm3 in the target, / is the beam beam, odd (E) is the neutron production cross section of the dd fusion reaction as a function of the neutron beam energy E. The ionic species were weighted by their fraction fk and the number of nuclei k per ion. represents the braking power of the deuterium-charged target. The equation was numerically solved by discretizing the energy at 30 keV intervals and estimating the density of neutrons at target pc equal to 3.76 g.cm'3, based on the report. 1954 University of California technician entitled “Information on the Neutrons Produced in the H3 (d, n) He4” by Jack Benven iste and Jerry Zenger Bragg's Law was employed to determine the braking power at the target, it is presented by equation 2e and is described by Heaton, R .; Lee, H .; Skensved, P. and Robertson, B. in the Nuclear Instruments and Methods publication in Physics Research Section A: Accelerators, Spectrometers, Detectors and Assigned Equipment, 276 (3): 529-538, 1989). (2) where the index M represents the metal and d represents the deuterium in the target. Braking power values can be obtained using the Srim code.

After obtaining the neutron yield, Eq.1, for the neutron emission source distributed on the target, the neutron spatial distribution and its spectrum in the moderator volume is calculated in an attempt to evaluate the fast spectrum degradation (2 , 45 MeV emitted by dd, [) or example) in the thermal spectrum. In the regions where the samples are located, the macroscopic shock section of the material to be irradiated is obtained by multiplying the energy-dependent transmutation (η, γ) microscopic shock section (η, γ) by the neutron spectrum. , normalized by the neutron yield by the source, and finally by the volumetric density of atoms to be transmuted, to atoms-cm3. Then, the temporal and volumetric rate of R „of radioisotope transmutation, defined as, in nuctide units produced“ nr ”per unit volume, cm3, per unit fluency emitted by the source, ie n.s'1, is calculated. . This is multiplied by CTFTI yield γ and entered in equation 3 in order to define the sample activity as a function of the irradiation time t. (3) Where λ represents the half-life constant of radionuctfdeo, the product of transmutation. The volumetric transmutation rate Rv can then be obtained by equation 4. (4) where p represents the density of the sample material (Z), NA the Avogadro number, A is the atomic mass of the isotope-containing compound Z a be transmuted, ω is the chemical fraction multiplied by the isotopic fraction of the isotope Z in the compound, and oz (E) the neutron absorption shock section of the isotope in question and Φ (Ε, γ) the neutron flux in the moderated position r (from the sample), both energy dependent, and γ the neutron yield generated by dd reactions, which means the appearance of neutrons at the target. The term <σζ (Ε) φ (Ε, Γ)> / γ is evaluated by the MCNP code at a given moderator position r, and integrated into the energy spectrum domain between thermal energy at 2,5 MeV. calculations for some samples are given in the examples.

Regarding the plasma contained in the non-thermalized plasma chamber (10) produced in the low temperature plasma chamber (10). These can be generated by continuous, pulsed or pulsed electrical discharges, capacitively and inductively coupled with radio frequency discharges, antenna discharges, and microwave discharges in closed cavities, or even in open structures. Coupled capacitive discharge can occur between two parallel plates or transverse electrodes in which an alternating potential difference is applied. Coupled inductive discharge is generated by induction of a coil. Plasma 10 may also be generated by a strong electromagnetic field applied with a laser or microwave generator, or by applying a strong electric field to a gas where Townsend's avalanche process occurs. Townsend's discharge process is an ionization process where free electrons are accelerated by the electric field, strong enough to generate an electrical conduction in the gas in the form of an avalanche multiplication caused by the inactivations of ionized molecules and ions. RF radio frequency plasma generation is of interest when long-term operation is required. Electric discharges applied by the plasma generator may be classified by the frequency of the excited field and may range from kHz to MHz, classified as: by direct current (DC) discharges; pulsed DC discharges (kHz); radio frequency discharges (MHz), supported by ohmic and stochastic electron heating mechanisms; by microwave discharges (GHz); by laser generated plasma; or by discharging oriented electron beams. In short, there are various forms of plasma generation, the science and technology of which is in the public domain. The alteration of the plasma generation form in the plasma chamber, described in this patent, while maintaining similar geometry, material or components, and preserving use, does not characterize a new invention, but merely represents modifications in the form of deuterium gas ionization supported by for scientific and technical information of common knowledge.

As an application, CTFTI can transmute and produce neutron-rich radionuclides, preferably from the group comprising: Na-24, P-32, S-35, CI-38, Ar-41, K-42, Ca-47, Ca-49, Ti-51, V-52, Cr-55, Mn-56, Fe-59, Co-60, Ni-65, Cu-64, Cu-66, Zn-69, Zn-71, Zn- 72, Ga-70, Ga-72, Ge-72, Ge-75, As-76, Se-81, Se-83, Br-80, Br-82, Kr-87, Kr-85, Kr-81, Kr-79, Rb-86, Rb-88, Sr-85, Sr-87, Sr-89, Sr-90, Y-90, Mo-99, Ru-105, Ru-106, Rh-104, Pd- 103, Pd-107, Ag-108, Ag-110, Ag-111, Ag-113, Cd-111, Cd-115, Cd-117, In-114, In-116, In-114, In-116, Sn-125, Sn 121, Sn-123, Sb122, Sb123, Sb125, Te-121, Te123, Te125, Te-127, Te-129, Te-131, 1-128, 1-131, Xe-125, Xe -127, Xe-129, Xe-131, Xe-133, Xe135, Xe-137, Cs-134, Ba-133, Ba-135, Ba-139, Ba-'30, La-140, Ce-137, Ce-139, Ce-141, Ce-143, Pr-142, Pr-143, Nd-147 Nd-149, Nd-151, Sm-151, Sm-153, Sm-155, I-152, I-154 , I-155, I-156, Gd-53, Gd-159, Gd-161, Tb-160, Dy-157, Dy-159, Dy-165, Dy-166, Ho-166, Er-39 , Er-171, Tm-170, Yb-169, Yb-175, Yb-177, L U-177, Hf-175, Hf-181, Hf182, Hf-177, Hf-178, Hf-179, Ta-182, W181, W185, W-187, W188, Re-188, Os-193, 1r- 192, lr-193, lr-194, Pt-191, Pt-193, Pt-195, Pt-197, PM 99, Au-1998, Au-199, Hg-197, Hg-199, Hg-203, Hg -205, Ti-204, Ti-206, Pb-205, Pb-209, Bi-201, Bi-211, Th-233, U-239. The CTFTI cell can also be applied as a transmutator of one or more of the half-life radionuclides, precursor of a half-life radionuclide, which pair is defined in the group comprising: Μο-99 / Tc-99m, Sr-90 / Y-90, Rb-81 / Kr-81m, Hg-195 / Au-195m; W-188 / Re-188, Si-32 / P-32, without limitation. The CTFTI cell can eliminate radioactive waste by producing short half-life nuclides in the transmutation of half-life nuclides from the californium, berkelium, curium, americium, plutonium, neptune, uranium, protactinium, thorium, actinide, radio, strontium, iodine, cesium, cobalt, iron, sodium, without limitation, commonly existing and produced in nuclear fuels in nuclear reactors. CTFTI can also transmute fissionable nuclides into fissiles, such as Th-232 on U-233 and U-238 on Pu-239.

Samples of holmium silicate brachytherapy seeds in Si: Ho: Ca composition can be activated in CTFTI. Si: Sm: Ca ceramic seed radio 153Sm can be activated on the CTFTI device. Then CTFTI can be employed in activating radioactive seeds for brachytherapy, including bivovert-based ceramic seeds, or oxide, phosphate, silicate, carbonate-based nanoparticles, phytates or macroaggregates, as well as nitrate and chloride-based radioactive inputs, or polymers incorporating X-ray, gamma or beta-ray emitting radioisotopes, without limitation. The present technology may be better understood by the following non-limiting examples.

Example 1: CTFTI Electromagnetic Assessment

As an example of electromagnetic evaluation, we present the electrical potential distribution of a simulated CTFTI in the Computer Simulation Technology (CST) code. In this, an electric potential of 30 kV was used in the plasma electrode (13) and -150 kV in the target electrode (11). The profile of equipotential lines is shown in Figure 8.

As a result of the simulation, Figure 9 shows the energetic profile of the neutron beams, representing their trajectories towards the target. The presented configuration allowed to reach a current of 1,621 A of neutrons in each target, which allows the generation of a neutron flux suitable for transmutation in the sample receptacles.

Example 2: CTFTI Neutron Evaluation

As an example of nuclear evaluation, we present the CTFTI model, simulated in code MCNP5 (Monte Carlo N-Particle). The materials used in this evaluation were: dry air (external environment), shielding (borated polyethylene, density 1.12 g cm'3), reflector (Cromel density 10.27 g cm'3), receptacles (steel stainless steel, density 8.0 g cm'3), insulator (kaolinite, 2.50 g cm'3), plasma chamber filled with deuterium gas (density 0.01 g cm'3), plasma electrodes and target (copper, density 8.50 g.cm'3), deuterium gas acceleration environment (at 0 001 g.cm3), target (copper, titanium deuterium, 8.50 g cm'3), reflector ( of bispnuto and lead alloy, density 10,27 g cm-3), and moderator (graphite, 1,70 g cm-3, and light water, 1,0 g cm-3).

The values obtained for the total flux in the periphery were 2Í83617.103 and in the moderator center of 2.4091.10 3 multiplied by the appearance of neutrons emitted by the source, represented by the reaction rate of c-d. Thus, a flux of 2.8 101 ° n.cm2.s "1 is expected for an appearance of 'O13 n.s'1. The neutron flux in the moderator was one of the requests requested in code MCNP5, which executed neutron transport in CTFTI, being moderated from fast to thermal energies in the moderator volume.

Example 3: Evaluation of the Neutral Flow Energy Profile Figure 11 shows the neutron flow spectrum at the center of the CTFTI and at the moderator edge, 3m away from the edge, near the target electrode. In the center of the moderator, the amount of fast neutrons of 2.5 MeV decreases and the number of thermal neutrons of less than 0.1 eV increases. This change in the neutron spectrum will help to increase the transmutation rate of the isotopes of interest.

Example 4: Production of radioactive molybdenum in column is in the moderator Considering the target composed of a deuterized titanium tape deposited on a metallic target of titanium or copper, consisting of a 1 mm film, for example. The TiDx composition where x can assume different values depending on the temperature and concentration of deuterium in the target. For TiDx (x = 4), for example, the molecular weight will be 59.9 g / mol. With a TiDx mass density of 4.5 g.cm-3, the target is expected to have 1.81 x 1022 deuterium atoms per cm3. The dd reaction shock section is 70mb, ie 7.00 x 10 "26 cm2. And the macroscopic shock section is 0.0127 cm -1. A deuterium intensity of 1 mA.crrf2 represents 6, 24 1015 deuteriums per s cm2 The volumetric reaction rate is 7.91 x1013 n.s'1cm'3 A target surface cm2 exposes 10'4 cm3 TiDx, representing an appearance of 7.91 x109 n s '1 per cm2 of the target. A 10 cm radius, 5 cm long target, for example, is 1571 cm2. This represents a current of 1.571 A and produces an appearance of 7.91 x1012 n s'1. neutron appearance is generated as a source around the moderator From this information it is possible to evaluate the reaction rate of samples internally positioned in the cylindrical moderator.

Considering a nuclide to be transmuted into a sample of apparent mass density of 1.0 g.cm3, which is Mo-98, in the form of Mo-Zr, at a concentration of 100 mg.g-1 of Mo-98. Thus, the percentage of Mo in the sample is 10% by weight. The metal-ceramic matrix composite is formed as zirconium molybdenum powder to be irradiated in columns in the transmutant cell. 30 columns of 3 cm in diameter and 10 cm in length will have a volume of 2 Liters, with a Mo-98 mass of 200 g, referring to a nuclide density of 0.000614592 atoms / b-cm. The interaction rate represented by neutron flux multiplied by the Mo-98 microscopic shock section in the central region generated in a sphere positioned in the moderator was 0.00051925 cm'1n "1 (n = neutron emitted by source) Multiplying this value by the appearance of neutrons at source and the density of nuclides in the sample receptacle yields 1.23 x 108 reactions.s'1cm'3, which represents 7.06 Ci.s'1, for thirty dolunas. internally arranged in the moderator Each column will be continuously producing, in secular equilibrium, 230 mCi of radioactive Mo, which under normal elution conditions produces 80% of this activity in 99mTc radioactive technetium.

Claims (3)

1) FUSER CELL, characterized in that it comprises a device consisting of a plasma generator contained in a plasma chamber (10) of toroidal geometry containing ionized deuterium gas, with cylindrical cross-section of internal radius of 2 to 50 cm and longitudinal section with average radius of 5 to 200 cm, having part of its cross-section limited by a cylindrical surface, with the radius ranging from 5 to 200 cm and length of 10 to 100 cm, composing the surface of the plasma electrode (13) as a cylindrical segment, and a thickness of 0.1 to 1 cm, having from 1 to 100 spherical openings per square centimeter of radius ranging from 0.1 to 1 cm, whose openings are oriented toward the target electrode (11) internal to the toroid; may be followed by the suppression electrode (131) and the containment electrode (132); indoor (176) or outdoor (177) radio frequency antenna; a metal hydride target, incorporated with deuterium (d) or tritium (t), shaped like a cylindrical ring or toroidal section composing the target electrode (11), with an inner section radius of 2 to 50 cm, and length from 2 to 100 cm; thermal refrigerant and electrical insulator (162) circulating behind the target electrode (11); the neutron moderating material (15), confined between the electrical insulator (162) and the sample receptacles (161), in a solid cylindrical shape with a radius ranging from 5 to 200 cm and a length of 10 to 300 cm; where one or more sample receptacles (161) are of cylindrical shape with radius ranging from 2 to 5 cm and thickness from 0.1 to 1 cm and length from 3 to 300 cm; cable holder and accessories (163) covering the sample receptacles (161), protective plate (164), and externally the cell is confined by annular cylindrical reflective material (16); and by annular cylindrical shield (160) with upper cover (18) composed of reflective material (16) and shield (160), where sample insertion perforations (17) may be added; having reflector or shield thicknesses of 10 to 50 cm, forming a cell bounded by a cylindrical surface, with a radius of 10 to 300 cm and a length of 10 to 200 cm; this cell being composed of the target (11) and plasma (13) electrodes, and optional, constructed of metal parts, composing surfaces of copper, aluminum, titanium, or their alloy; the target (11) being represented by a metallic film deposited on the target electrode (11), composed of metal hydride being this target deuterized in a matrix of titanium, copper, gold, silver, or tungsten; the moderator (15) consisting of low atomic weight neutron moderating material such as light water (H20), heavy water (D20), graphite, high density polymers, fluorinated polymers, polyethylene, teflon, beryllium, sulfur compounds, or mixtures thereof; the reflector (16) consisting of material composed of chromium, copper, bismuth, lead, tungsten carbide or alloys or mixtures thereof; electrical insulators (165) consisting of electrical insulating material, which may cover the unexposed face of the target electrode, electrode joints and edges, and electrical connections (172) from the high voltage system (171) and radio frequency connections and radio frequency system isolator (175) between these conductive materials and other parts of the device consisting of dielectric material such as glass, special ceramics and rubber; refrigerant (162) consisting of a thermal and electrical insulating coolant for the target (11), such as insulating mineral or organic oil; the shield (160) composed of polyethylene, water, or graphite, mixed with neutron absorbing substances such as boron, lithium, cadmium or gadolinium, and coated with bismuth, lead or tungsten carbide; and valves (178) and the gas cylinder (179) that fills the plasma chamber (10) is neutral deuterium gas, or enriched with gaseous tritium. FUSER CELL according to claim 1, characterized in that the moderator shell (15) and the sample receptacles (161) can be a single element, so that the divo nuclides can be inserted and combined in the moderator (15). FUSER CELL according to claims 1 and 2, characterized in that it is connected to a radio frequency (RF) system (175), with a radio frequency connection and isolator (170), to a high voltage system (171) with high voltage power connections (172) to the electrodes, a deuterium gas supply system (D2) (178).