CN112599282B - Fusion reactor cladding for producing Pu-238 isotope - Google Patents
Fusion reactor cladding for producing Pu-238 isotope Download PDFInfo
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- CN112599282B CN112599282B CN202011353233.1A CN202011353233A CN112599282B CN 112599282 B CN112599282 B CN 112599282B CN 202011353233 A CN202011353233 A CN 202011353233A CN 112599282 B CN112599282 B CN 112599282B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Abstract
The invention relates to a fusion reactor cladding for producing Pu-238 isotopes, which comprises a cladding armor, a cladding first wall, a group of multiplication regions and proliferation regions or more than two groups of multiplication regions and proliferation regions which are arranged in a staggered mode, a graphite slowness layer, a neptunium target layer, a graphite reflection layer and an outermost shielding layer in the radial direction far away from a source, wherein a partition plate is arranged between the multiplication regions and the proliferation regions. The reaction cladding provided by the invention can reduce the construction and operation cost of the production process, ensure the safety of production facilities and equipment and reduce the possibility of potential risks on the basis of meeting engineering requirements.
Description
Technical Field
The invention belongs to the technical field of radioactive waste treatment, and particularly relates to a fusion reactor cladding for producing Pu-238 isotopes.
Background
The post-treated spent fuel contains about 95% uranium and 1% plutonium, and also about 4% long-life fission products and minor actinides Np, am and Cm, etc. (Np about 0.1% of the total mass). Among them, np-237 is a fissile nuclear material, which is second to uranium and plutonium in importance in the nuclear industry, and can be made into a target material to be irradiated in a neutron irradiation device to produce an important α radioisotope Pu-238.
Plutonium-238 (Pu-238) is an excellent source of alpha radioisotope energy, can be used to manufacture isotope batteries for satellites and medical cardiac pacemakers, and has the advantages of high specific power (up to 0.5W/g), long half-life (87.7 years), weak gamma radiation, and easy shielding. In addition, as Pu-238 can also emit X-rays with lower energy, the low-energy photon source can also be prepared, and an isotope neutron source can also be produced by utilizing alpha particles released by the low-energy photon source. Thus, the demand for Pu-238 will increase day by day.
At present, the method for producing Pu-238 by irradiating neptunium targets with neutrons is wider and has higher production efficiency. The process for producing Pu-238 from Np-237 (e.g., npO2 oxide of Np-237) comprises processing NpO2 powder, pressing into a target shell, and hermetically packaging into a target. The neptunium target is irradiated in a reactor, and Np-237 captures a neutron and emits gamma rays to form Np-238. The half-life of Np-238 is 2.1 days, beta decays to obtain Pu-238, and the reactions are shown as formula (1) and formula (2). Pu-238 will continue to capture neutrons, generating heavier isotopes of Pu, such as Pu-239, pu-240, pu-241, and Pu-242, among others.
The nuclear reaction of Np-237 to Pu-238 after neutron irradiation in the reactor is not unique but is accompanied by a series of side reactions. These side reactions directly affect the efficiency and yield of Pu-238. Although these side reactions are unavoidable, the target can be made by taking measures or selecting appropriate irradiation equipment, neutron fluence, irradiation time, neutron energy spectrum for improving irradiation, etc., to minimize the probability of side reactions, thereby increasing the quality and yield of Pu-238 and avoiding unnecessary consumption of Np-237 and Pu-238.
Research shows that when the neutron energy range of the irradiation device is within 0.5eV-5eV, the production efficiency and the yield of the Np-237 are optimal. At present, domestic commercial power stations in service are mainly pressurized water reactors, the neutron spectrum distribution of the reactor core of the pressurized water reactor is relatively complex, the average energy range of fission neutrons of a fuel assembly (fission spectrum) of the pressurized water reactor is about 2MeV, the energy range of the neutron spectrum of the reactor core from 0.5eV to 5eV is relatively small, and the production efficiency and the yield of Pu-238 prepared by irradiating neptunium targets are relatively low. And irradiating the neptunium target in the reactor may be accompanied by supercritical and other operational safety issues and risks. The irradiation time of Pu-238 output is greatly different from the operation history of the pile, and the running and production economy of the pile is poor due to frequent pile stopping. The reactors of commercial pressurized water reactor power plants are not suitable for irradiation production of Pu-238.
At present, the fusion reaction between deuterium (2D) and tritium (3T) is utilized to generate neutrons with single energy (14 MeV), and the fusion reaction between deuterium and tritium is shown in formula (3) in the Tokomak fusion device which is being researched and built at home and abroad. The neutron energy spectrum of a radiation source of the fusion reactor is much simpler than that of a fission reactor, and after certain absorption and moderation, the proportion of the neutron distribution in the energy range of 0.5eV-5eV can be maintained at a higher level, so that the production efficiency and the quality of Pu-238 are improved.
2 D+ 3 T→ 4 He+n(14MeV)+3.43MeV…………(3)
Through calculation analysis and research, the prepared neptunium target is arranged at a specific position in a reaction envelope of a fusion reactor, and Pu-238 can be produced on a large scale on the basis of not influencing the reactor operating power and tritium production. And the characteristics of the fusion reactor determine that the scheme has no supercritical and other operation safety problems and risks and has special inherent safety. By organically combining the operation history of the fusion reactor and the technical scheme of cladding replacement, the production efficiency and quality of Pu-238 can be effectively improved, unnecessary consumption of raw materials is avoided, and the economical efficiency of the production process is obviously improved.
In conclusion, the fusion reactor cladding for producing Pu-238 has the following advantages compared with a fission reactor (the main reactor type in China is a pressurized water reactor):
the neutron source has single energy (14 MeV), and after certain absorption and moderation, the proportion of neutrons distributed in the energy range of 0.5eV to 5eV can be maintained at a higher level, so that the yield and the quality of Pu-238 are improved; the operating history of the heap is different from that of a fission heap and can be unloaded from the heap and taken out when the yield of Pu-238 reaches the peak value; the influence of the operation of extracting products on the operation of the pile is very small, and the economic cost of the operation of the pile cannot be increased; the loading scheme is simple, possible supercritical and other operation safety problems and risks do not exist, and the complicated reactor core loading scheme design is not needed like a fission reactor; besides the inherent safety, the number of the loading targets can be increased, the loading scheme is simplified, and the economic cost is reduced. However, there is a certain safety risk in producing Pu-238 by using the fusion reactor cladding, and especially, the realization of industrial scale production has higher requirements on the stability of the fusion reactor cladding. Therefore, the fusion reactor cladding layer which is reasonable and feasible and can stably produce Pu-238 is provided, and the problems that the safety risk exists in the irradiation scheme of the fission reactor is utilized, the industrial scale production requirement is difficult to achieve and the like are solved.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a fusion reactor cladding for producing Pu-238 isotopes, so as to reduce the construction and operation cost of the production process, ensure the safety of production facilities and equipment and reduce the possibility of potential risks on the basis of meeting engineering requirements.
In order to achieve the above purposes, the invention adopts the technical scheme that: the fusion reactor cladding structure comprises a cladding armor, a cladding first wall, a group of multiplication region and multiplication region or more than two groups of multiplication region and multiplication region which are arranged in a staggered mode, a graphite slowness layer, a neptunium target layer, a graphite reflection layer and an outermost shielding layer in the radial direction far away from a source, and a partition plate is arranged between the multiplication region and the multiplication region.
Further, the material of the cladding armor is beryllium metal or tungsten metal.
Further, the material of the cladding first wall is low activation austenitic stainless steel or martensitic stainless steel.
Further, the inside of the first wall of the cladding is provided with a cooling water pipe.
Further, the thickness of the first wall material of the cladding layer is 6mm-20mm.
Further, the multiplication region is made of metallic beryllium, and the multiplication region is made of lithium titanate or lithium silicate.
Furthermore, the material of the baffle is low activation austenite stainless steel or martensite stainless steel, and a cooling water pipeline is arranged inside the baffle.
Further, the material of the graphite slowing-down layer is graphite; the graphite reflecting layer is made of graphite.
Further, the material in the neptunium target layer is NpO 2 Powder or NpO 2 And (5) blocking.
Further, the material of the outermost shielding layer of the cladding structure is low-activation austenitic stainless steel or martensitic stainless steel.
The fusion reactor cladding for producing Pu-238 isotope provided by the invention has the following advantages:
1. realizing the large-scale production of Pu-238. Because the neutron energy of the fusion reactor radiation source is single, the proportion of the moderated neutrons distributed in the energy range of 0.5eV to 5eV is maintained at a higher level, thereby ensuring the yield and quality of Pu-238 and ensuring that the Pu-238 can be continuously produced in a large scale.
2. The economical efficiency of the production process is improved. The production efficiency and the quality of Pu-238 can be improved by organically combining the technical scheme of fusion reactor operation history and cladding replacement, the unnecessary consumption of raw materials is reduced to the maximum extent, and the generation of other radioactive isotopes is reduced.
3. Has special inherent safety. The characteristics of the fusion reactor determine that the scheme has no supercritical and other operation safety problems and risks. Fusion reactor is using deuterium ( 2 D) With tritium ( 3 T), without the risk of overcritical risks due to uncontrolled reactivity of the reactor by the addition of neptunium targets, as in the case of a fission reactor, and without affecting the normal operation of the reactor.
4. Is convenient for operation and easy for extraction. When the cladding is replaced, the irradiated neptunium target can be extracted in time, and complicated operations such as fission reactor operation (such as shutdown for opening the top cover of the pressure vessel, transferring fuel assemblies, reactor internals, instruments and the like) do not exist. Due to the difference of the operation histories of the fusion reactor and the fission reactor, pu-238 can be extracted by replacing cladding under the condition of ensuring the operation power and tritium yield. This may further improve the economics of the production process.
Drawings
FIG. 1 is a schematic diagram of a Tokomak fusion reactor half-section in the longitudinal direction and the cladding position and arrangement as described in the embodiments of the present invention;
FIG. 2 is a schematic illustration of a cross-section of a cladding structure according to an embodiment of the present invention; in the figure: the solar cell comprises a 1-cladding armor, a 2-cladding first wall, a 3-multiplication region, a 4-multiplication region, a 5-partition plate, a 6-graphite slowing layer, a 7-neptunium target layer, an 8-graphite reflecting layer and a 9-shielding layer.
Detailed Description
The invention is further described with reference to the following figures and detailed description.
As shown in fig. 1 and fig. 2, the fusion reactor cladding for producing Pu-238 isotope provided by the present invention has an integral module structure, and has a layered structure of different materials along the radial direction of the cladding, the layers are tightly attached to each other, and the cladding includes a cladding armor 1, a first wall 2 of the cladding, more than two groups of multiplication regions 3 and multiplication regions 4 arranged alternately, a graphite moderation layer 6, a neptunium target layer 7, a graphite reflection layer 8 and an outermost shielding layer 9 along the radial direction far from the source, and a partition 5 is provided between the multiplication regions 3 and 4; the cladding is placed at a specific position of the Tokomak fusion reactor.
In other embodiments of the present invention, the number of multiplication regions 3 and multiplication regions 4 may be one.
The cladding armor 1 is made of metal beryllium or tungsten and is used for protecting the cladding, relieving the impact of high-energy neutrons on the cladding and playing a certain role in neutron moderation. The thickness of the metal beryllium or tungsten used for the cladding armor 1 is 0.5mm-15mm, and the shape, the geometric dimension, the position and the like of the metal are related to actual equipment parameters.
The cladding first wall 2 is made of low-activation austenitic stainless steel or martensitic stainless steel (cooling water pipelines are arranged inside the cladding first wall) and is used for energy conversion and plays a role in primary neutron absorption and moderation. The low activation austenitic stainless steel or martensitic stainless steel used for the cladding first wall 2 (with the cooling water pipes arranged inside) has a thickness of 6mm-20mm, and its shape, geometry and position etc. are related to the actual equipment parameters.
A plurality of multiplication regions 3 and multiplication regions 4 in the cladding structure are arranged in a staggered mode, and partition plates 5 are arranged between the multiplication regions and the multiplication regions. The multiplication regions 3, the multiplication regions 4 and the partition plates 5 in the cladding structure are used for ensuring the operating power and tritium production of the reactor and further slowing down higher-energy neutrons.
The material of the cladding multiplication region 3 adopts metallic beryllium, the material of the multiplication region adopts lithium titanate or lithium silicate, and the material of the clapboard (the inside of which is provided with a cooling water pipeline) adopts low-activation austenitic stainless steel or martensitic stainless steel. The thicknesses of the materials of the multiplication region 3, the multiplication region 4 and the partition plate 5 of the cladding structure are the minimum thicknesses which satisfy the operating power and tritium yield of the stack comprehensively and enable neutrons of the neptunium target layer to be distributed at the optimal level condition within the energy range of 0.5eV-5eV, and the shape, the geometric dimension, the position and the like of the materials are related to actual equipment parameters.
The material of the graphite slowing-down layer 6 is graphite and is used for slowing down neutrons. The material thickness of the graphite slowing layer 6 is the minimum thickness which maximizes the proportion of the neptunium target layer distributed in the energy range of 0.5eV-5 eV.
The material in the neptunium target layer 7 is NpO2 powder/block, the material thickness of the neptunium target layer 7 is such as to optimize Pu-238 yield and quality, and its shape, geometry and position are related to the actual plant parameters.
The graphite reflecting layer 8 is made of graphite, and the thickness of the graphite reflecting layer 8 enables the utilization efficiency of reflected neutrons to be highest.
The shielding layer 9 is made of low-activation austenitic stainless steel or martensitic stainless steel, the cladding structure shielding layer 9 plays a role in shielding and absorbing neutrons and a certain role in reflecting neutrons, and the thickness of the material of the shielding layer 9 enables the accumulated neutron fluence of a structure (such as a superconducting coil) outside the shielding layer in the service life to meet the design requirements.
The above-described embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (7)
1. A fusion reactor cladding for producing Pu-238 isotope is characterized in that the cladding is of an integral module structure and is of a layered structure made of different materials along the radial direction of the cladding, the fusion reactor cladding sequentially comprises a cladding armor, a cladding first wall, a group of multiplication region and multiplication region or more than two groups of multiplication region and multiplication region which are arranged in a staggered mode, a graphite slowing layer, a neptunium target layer, a graphite reflecting layer and an outermost shielding layer along the radial direction far away from a source, and a partition plate is arranged between the multiplication region and the multiplication region; the multiplication region is made of metallic beryllium, and the multiplication region is made of lithium titanate or lithium silicate; the material of the partition board is low-activation austenitic stainless steel or martensitic stainless steel, and a cooling water pipeline is arranged inside the partition board; the material in the neptunium target layer is NpO 2 Powder or NpO 2 And (5) blocking.
2. A fusion reactor cladding for producing an isotope of Pu-238 as claimed in claim 1 wherein said cladding armour material is metallic beryllium or metallic tungsten.
3. A fusion reactor cladding layer for producing an isotope of Pu-238 in accordance with claim 1 wherein the material of said cladding first wall is low activation austenitic stainless steel or martensitic stainless steel.
4. A fusion reactor cladding for producing Pu-238 isotope according to claim 1 or 3, wherein said cladding first wall is internally provided with cooling water conduit.
5. A fusion reactor cladding for producing Pu-238 isotope according to claim 1 or 3, wherein the thickness of the cladding first wall material is 6mm to 20mm.
6. A fusion reactor cladding for producing an isotope of Pu-238 as claimed in claim 1 wherein said material of said graphite moderating layer is graphite; the graphite reflecting layer is made of graphite.
7. A fusion reactor cladding for producing Pu-238 isotope according to claim 1, wherein the outermost shield layer of said cladding structure is of low activation austenitic stainless steel or martensitic stainless steel.
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Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4370295A (en) * | 1978-03-21 | 1983-01-25 | Fdx Associates, L.P. | Fusion-fission power generating device having fissile-fertile material within the region of the toroidal field coils generating means |
| US4663110A (en) * | 1982-03-12 | 1987-05-05 | Ga Technologies Inc. | Fusion blanket and method for producing directly fabricable fissile fuel |
| CN103093836A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Fusion driving subcritical cladding of transmutation subordinate actinium series nuclide |
| CN103578574A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core tritium-production blanket |
| CN103578579A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core |
| JP2018124178A (en) * | 2017-02-01 | 2018-08-09 | 株式会社東芝 | Blanket for nuclear fusion reactor, blanket support mechanism, formation method of cooling water channel inside housing wall, blankety module assembly method, and blanket support structure assembly method |
| CN110706840A (en) * | 2019-10-18 | 2020-01-17 | 中国科学院合肥物质科学研究院 | Accelerator driving based99Mo subcritical production device and method |
| CN111950177A (en) * | 2020-07-22 | 2020-11-17 | 核工业西南物理研究院 | Multi-physical-field coupling neutron automatic optimization method for solid tritium production cladding |
-
2020
- 2020-11-27 CN CN202011353233.1A patent/CN112599282B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4370295A (en) * | 1978-03-21 | 1983-01-25 | Fdx Associates, L.P. | Fusion-fission power generating device having fissile-fertile material within the region of the toroidal field coils generating means |
| US4663110A (en) * | 1982-03-12 | 1987-05-05 | Ga Technologies Inc. | Fusion blanket and method for producing directly fabricable fissile fuel |
| CN103093836A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Fusion driving subcritical cladding of transmutation subordinate actinium series nuclide |
| CN103578574A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core tritium-production blanket |
| CN103578579A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core |
| JP2018124178A (en) * | 2017-02-01 | 2018-08-09 | 株式会社東芝 | Blanket for nuclear fusion reactor, blanket support mechanism, formation method of cooling water channel inside housing wall, blankety module assembly method, and blanket support structure assembly method |
| CN110706840A (en) * | 2019-10-18 | 2020-01-17 | 中国科学院合肥物质科学研究院 | Accelerator driving based99Mo subcritical production device and method |
| CN111950177A (en) * | 2020-07-22 | 2020-11-17 | 核工业西南物理研究院 | Multi-physical-field coupling neutron automatic optimization method for solid tritium production cladding |
Non-Patent Citations (1)
| Title |
|---|
| 聚变实验增殖堆He冷包层中子学设计研究;吴宜灿，孔明辉，邱励俭;《核科学与工程》;19960630(第02期);论文章节1-2、图1 * |
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