CN108470589B - Fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-service-life fission products - Google Patents
Fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-service-life fission products Download PDFInfo
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- 230000004992 fission Effects 0.000 title claims abstract description 72
- 229910052768 actinide Inorganic materials 0.000 title claims abstract description 54
- 150000001255 actinides Chemical class 0.000 title claims abstract description 54
- 238000001228 spectrum Methods 0.000 title claims abstract description 21
- 238000010438 heat treatment Methods 0.000 title abstract description 9
- 238000009377 nuclear transmutation Methods 0.000 claims abstract description 97
- 239000000446 fuel Substances 0.000 claims abstract description 89
- 230000035755 proliferation Effects 0.000 claims abstract description 31
- 239000000203 mixture Substances 0.000 claims abstract description 18
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 17
- 229910002804 graphite Inorganic materials 0.000 claims abstract description 17
- 239000010439 graphite Substances 0.000 claims abstract description 17
- 238000005253 cladding Methods 0.000 claims abstract description 16
- 239000000463 material Substances 0.000 claims abstract description 14
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 13
- 229910052580 B4C Inorganic materials 0.000 claims abstract description 4
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims abstract description 4
- 238000006243 chemical reaction Methods 0.000 claims description 12
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 11
- 230000000712 assembly Effects 0.000 claims description 10
- 238000000429 assembly Methods 0.000 claims description 10
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 claims description 6
- 239000002826 coolant Substances 0.000 claims description 6
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 6
- 229910052685 Curium Inorganic materials 0.000 claims description 3
- 229910052781 Neptunium Inorganic materials 0.000 claims description 3
- GKLVYJBZJHMRIY-OUBTZVSYSA-N Technetium-99 Chemical compound [99Tc] GKLVYJBZJHMRIY-OUBTZVSYSA-N 0.000 claims 1
- ZCYVEMRRCGMTRW-NJFSPNSNSA-N iodine-129 atom Chemical compound [129I] ZCYVEMRRCGMTRW-NJFSPNSNSA-N 0.000 claims 1
- RUDFQVOCFDJEEF-UHFFFAOYSA-N yttrium(III) oxide Inorganic materials [O-2].[O-2].[O-2].[Y+3].[Y+3] RUDFQVOCFDJEEF-UHFFFAOYSA-N 0.000 claims 1
- 239000002699 waste material Substances 0.000 description 7
- 238000005516 engineering process Methods 0.000 description 4
- 230000004907 flux Effects 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- 241000894007 species Species 0.000 description 3
- 241000282412 Homo Species 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000006378 damage Effects 0.000 description 2
- 230000004927 fusion Effects 0.000 description 2
- 229910052734 helium Inorganic materials 0.000 description 2
- 239000001307 helium Substances 0.000 description 2
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 2
- 239000002927 high level radioactive waste Substances 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000008188 pellet Substances 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 229910052727 yttrium Inorganic materials 0.000 description 2
- VWQVUPCCIRVNHF-UHFFFAOYSA-N yttrium atom Chemical compound [Y] VWQVUPCCIRVNHF-UHFFFAOYSA-N 0.000 description 2
- 241000282414 Homo sapiens Species 0.000 description 1
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000009395 breeding Methods 0.000 description 1
- 230000001488 breeding effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000003337 fertilizer Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000013077 target material Substances 0.000 description 1
- 238000010809 targeting technique Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
- G21C5/126—Carbonic moderators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a rapid-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-life fission products, which sequentially comprises a minor actinides transmutation region, a fissionable fuel proliferation region, a long-life fission product transmutation region, a reflecting layer region and a shielding layer region from the center of the reactor core to the outside, wherein the minor actinides transmutation region takes a mixture of MOX and MA as fuel; the fissionable fuel proliferation zone is fuelled with MOX; the long-life fission product transmutation area takes a mixture of UO 2 and LLFP as fuel, and a graphite slowing layer is added in the fuel assembly wall and the fuel rod cladding; the reflecting layer and the shielding layer are composed of graphite, boron carbide and structural materials. The high-energy neutrons of the reactor core are transmuted into MA in a minor actinide nuclide transmutation area, the proliferation of nuclear fuel is realized in a fissionable fuel proliferation area, and the nuclear fuel is slowed down into low-energy neutrons by a graphite layer in a fuel assembly wall and a fuel rod cladding when entering a long-service-life fission product transmutation area, so that LLFP can be effectively transmuted, the neutron utilization rate is improved, and the transmutation of minor actinide nuclides and long-service-life fission products can be realized while the productivity is improved.
Description
Technical Field
The invention belongs to the technical field of nuclear engineering, and particularly relates to a critical reactor core for simultaneously transmuting minor actinides and long-life fission products.
Background
The tremendous development of nuclear power provides a large amount of clean energy for humans, and also presents a number of social and environmental problems. Among the most urgent ones is the large amount of high-level waste generated by the operation of nuclear power plants, which if improperly disposed can cause unpredictable radioactive hazards to humans and other living things of the earth. Particularly, long-life high-level wastes in spent fuel, including minor actinides such as Np, am and Cm (MA for short), and long-life fission products such as 99 Tc and 129 I (LLFP for short), not only restrict the development of nuclear energy, but also form long-term harm to human beings.
There are currently three suggested nuclear waste disposal schemes internationally, including "one-pass", "closed cycle" and "separation-transmutation". The "one-pass" refers to the spent fuel being cooled and buried in the ground after being discharged from the reactor, and the "closed cycle" refers to the process of after-treatment after the spent fuel is cooled briefly, recovering uranium and plutonium in the spent fuel, and then solidifying the rest of the spent fuel. The two schemes have the advantages of low cost and large uncertainty, on one hand, the resource waste is caused, and on the other hand, the spent fuel can possibly reenter the biosphere for circulation at any time, and the problem of long-term radioactivity risk exists. "separation-transmutation" refers to chemically separating high-level nuclear waste materials in spent fuel, including minor actinides (MA for short) and long-life fission products (LLFP for short), and converting these long-life high radionuclides into short-life nuclides or stable nuclides by neutron nuclear reactions, mainly neutron capture reactions (minor actinides and heavy isotopes can undergo fission reactions).
The research result shows that MA has a fission threshold, can be obviously fissile section above 1MeV, has larger fission capture ratio under fast neutron energy spectrum, and needs to consume a large amount of high-energy neutrons for transmutation, so MA is suitable for transmutation by adopting fast neutron piles. Whereas LLFP require transmutation of nuclides (mainly 99 Tc and 129 I, etc.) which are different from MA nuclides, the thermal neutron reaction cross section of these long-lived fission products is an order of magnitude higher than the fast neutron reaction cross section, so LLFP is suitable for transmutation with thermal neutron reactors.
In the research of an exemplary fast reactor (CDFR) in China, a sodium-cooled fast neutron spectrum reactor core is adopted, and LLFP transmutation components are proposed to be arranged in an outer layer area of a reflecting layer of the MA incineration fast reactor, and the transmutation of LLFP is carried out by utilizing leakage neutrons. Although the arrangement can effectively realize neutron thermalization, the single-placed LLFP transmutation components are limited, only one layer exists, and the transmutation requirements can not be met far; and LLFP transmutation can consume neutrons all the time, the reaction section is less, higher neutron flux is needed to realize high-efficiency transmutation, and whether the neutron flux level in a leakage area can guarantee to reach higher transmutation efficiency is further verified.
In Chinese patent 03152870.8 and Chinese patent CN 102623078A, the national academy of sciences plasma physics institute and national academy of sciences fertilizer material science institute disclose a method and a system for subcritical nuclear waste treatment and nuclear fuel production based on neutron proliferation of fissionable materials and a high-efficiency nuclear waste transmutation subcritical reactor core based on mixed energy spectrum respectively, and the functions of simultaneously transmuting MA and LLFP can be realized. However, these subcritical systems all need to generate spallation reaction or fusion reaction between high-energy protons and target materials to provide exogenous neutrons, and at present, neither the proton targeting technology nor the fusion technology can provide stable exogenous neutrons, and the two technologies are relatively expensive, so that related technologies need to be further developed.
Disclosure of Invention
The invention aims to solve the technical problems: the method overcomes the defects of the existing transmutation technology, provides a fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-life fission products, realizes the proliferation of nuclear fuel in a fissionable fuel proliferation area by transmuting MA in a minor actinides transmutation area, and further slows neutrons entering the long-life fission products transmutation area into low-energy neutrons by a graphite layer in a fuel assembly wall and a fuel rod cladding, can effectively transmute LLFP, improves the utilization rate of neutrons, realizes the simultaneous transmutation of minor actinides and long-life fission products, and adopts liquid metal as a cooling agent to carry out fission energy generated by the reactor core so as to achieve the purpose of capacity.
The technical scheme adopted for solving the technical problems is as follows: a rapid-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-life fission products, which sequentially comprises a minor actinides transmutation region, a fissionable fuel proliferation region, a long-life fission product transmutation region, a reflecting layer region and a shielding layer region from the center to the outside; the minor actinide nuclide transmutation area, the fissionable fuel proliferation area and the long-life fission product transmutation area are all provided with control components; the minor actinide transmutation area takes a mixture of MOX and MA as fuel, and high-energy neutrons of the reactor core transmute MA in the minor actinide transmutation area; the fissionable fuel proliferation area takes MOX as fuel, fast neutrons can cause fissionable nuclides 238 U to be fissionable nuclides 239 Pu finally, proliferation of nuclear fuel is realized, and partial neutrons can be used by the transmutation area; the long-life fission product transmutation area takes a mixture of UO 2 and LLFP as fuel, neutrons entering the long-life fission product transmutation area are far away from the center of a reactor core, and graphite layers are arranged in the fuel assembly wall and the fuel rod cladding, so that the long-life fission product transmutation area can be further slowed down into low-energy neutrons, most neutrons are relatively low in central neutron energy, the effective transmutation is LLFP, the neutron utilization rate is improved, and the simultaneous transmutation of minor actinides and long-life fission products is realized.
The high-energy neutrons of the reactor core are transmuted to MA in a minor actinide nuclide transmutation area, the proliferation of nuclear fuel is realized in a fissionable fuel proliferation area, and neutrons entering a long-life fission product transmutation area are further slowed down into low-energy neutrons by a graphite layer in a fuel assembly wall and a fuel rod cladding due to being far away from the center of the reactor core, most neutrons are lower than the energy of the central neutrons, so that the utilization rate of neutrons can be effectively transmuted LLFP, the simultaneous transmutation of minor actinide nuclides and long-life fission products is realized, and the liquid metal is used as a coolant to bring out fission energy generated by the reactor core, so that the purpose of capacity is achieved.
Wherein the minor actinide nuclear species transmutation area takes a mixture of MOX and MA as fuel, wherein MA is extracted from cooled reactor spent fuel and comprises Np, am and Cm nuclear species, and the nuclear species undergo a fission reaction with fast neutrons to become fission products.
The fissionable fuel proliferation area takes MOX as fuel, is formed by mixing UO 2 and PuO 2, and fissionable nuclide 238 U is converted into fissionable nuclide 239 Pu after neutrons are captured, so that nuclear fuel proliferation is realized.
Wherein the long-life fission product transmutation zone uses a mixture of UO 2 and LLFP as fuel, LLFP is 99 Tc and 129 I extracted from cooled reactor spent fuel; a moderating layer is disposed within both the fuel assembly wall and the fuel rod cladding, the moderating material being graphite.
Wherein the reflective layer region is composed of a layer of reflective layer, and the reflective material is filled with a zirconia/yttrium mixture.
The shielding layer region consists of two layers of shielding layer components, and the shielding material is boron carbide.
The reactor adopts liquid metal as a coolant to carry out the fission energy generated by the reactor core, so as to achieve the purpose of capacity.
Compared with the prior art, the invention has the advantages that:
(1) The rapid-heating mixed energy spectrum critical reactor core structure capable of simultaneously transmuting minor actinides and long-life fission products provided by the invention can effectively utilize neutrons in the region, improve the transmutation rate and the neutron utilization rate and realize the function of simultaneously transmuting MA and LLFP.
(2) The rapid-heating mixed energy spectrum critical reactor core structure capable of simultaneously transmuting minor actinides and long-life fission products provided by the invention has the advantages that the structures of fuel assemblies and fuel rods in a minor actinides transmutation area and a fissionable fuel proliferation area are similar, and the fuel rods and the fuel assemblies in the long-life fission product transmutation area are just adding graphite layers in cladding and assembly walls, so that the whole reactor core structure is simple, is similar to the structure of a traditional reactor, and ensures the economical and technical feasibility of the reactor.
(3) Compared with the subcritical nuclear waste treatment and nuclear fuel production method and system based on fissionable material neutron proliferation and the high-efficiency nuclear waste transmutation subcritical reactor core based on mixed energy spectrum disclosed in Chinese patent 03152870.8 and Chinese patent CN 102623078A respectively, the reactor core adopted by the invention has a simple structure, does not need external supply of exogenous neutrons, and can realize the function of simultaneously transmuting MA and LLFP by means of high-flux neutrons generated by fission reaction in the reactor core.
(4) Compared with the method for arranging LLFP transmutation components in the outer layer area of the reflecting layer of the MA incineration fast reactor in the Chinese Demonstration Fast Reactor (CDFR) study, the reactor core structure provided by the invention can be used for carrying out LLFP transmutation by utilizing leakage neutrons, can be used for placing more LLFP components at a time, ensures that larger neutron flux is used for transmutation LLFP, and achieves higher transmutation efficiency.
Drawings
FIG. 1 is a radial arrangement of the core of the present invention;
FIG. 2 is a core axial layout of the present invention;
FIG. 3 is a radial layout of a long life fission product transmutation zone fuel assembly according to the present invention;
FIG. 4 is a radial layout of the UO 2 and LLFP hybrid fuel rods of the present invention.
Detailed Description
The invention is further described below with reference to the drawings and the detailed description.
As shown in fig. 1, the rapid-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-life fission products provided by the invention is sequentially provided with a minor actinides transmutation zone 1, a fissionable fuel proliferation zone 2, a long-life fission product transmutation zone 3, a reflecting layer zone 4 and a shielding layer zone 5 from the center to the outside; the minor actinides nuclide transmutation zone 1, the fissionable fuel proliferation zone 2 and the long-life fission product transmutation zone 3 are all provided with control components. The total height of the reactor core is 3.45m, the diameter 5.565m, and the height of the active area is 1m. As shown in fig. 2, the heights of the active regions of the minor actinide nuclide transmutation region 1, the fissionable fuel proliferation region 2 and the long-service-life fission product transmutation region 3 are the same, and a reflecting layer 4 and a shielding layer 5 are respectively arranged at the upper end and the lower end of the active region along the axial direction. The minor actinide transmutation area 1 takes a mixture of MOX and MA as fuel, neutrons with energy higher than 1MeV in the reactor core undergo transmutation reaction with MA in the minor actinide transmutation area 1, and the reactor core energy spectrum hardening is promoted; the neutrons after partial hardening enter a fissionable fuel proliferation area 2 taking MOX as fuel, the fast neutrons can cause fissionable nuclides 238 U to be fissionable nuclides 239 Pu finally, the proliferation of nuclear fuel is realized, and the superfluous neutrons can be further utilized by a transmutation area; the long-life fission product transmutation area 3 takes a mixture of UO 2 and LLFP as fuel, neutrons entering the long-life fission product transmutation area 3 are far away from the center of a reactor core, most neutrons are low in energy relative to the neutrons in the center, graphite layers are arranged in the fuel assembly wall and the fuel rod cladding, the neutrons with low energy can be slowly changed into low-energy neutrons for a plurality of times before entering the fuel assembly and the fuel rod, effective transmutation LLFP is realized, and the addition of UO 2 can ensure that the long-life fission product transmutation area 3 has higher neutron flux. In this way, neutrons in the region can be effectively utilized by the minor actinide nuclide transmutation region 1, the fissionable fuel proliferation region 2 and the long-life fission product transmutation region 3, the transmutation rate and the neutron utilization rate are improved, the functions of simultaneously transmuting MA and LLFP are realized, and the liquid metal is used as a coolant to carry out the fission energy generated by the reactor core, so that the purpose of capacity is achieved.
Minor actinides transmutation zone 1: the minor actinide transmutation region 1 consists of 7 layers of hexagonal modules, in which are housed the fuel module 115 cartridges of the MOX and MA mixture, the control module 12 cartridges. The height of the fuel assembly is 3.8m, the center-to-center spacing of the assemblies is 198mm, the gaps of the assemblies are 4mm, and the wall thickness of the assemblies is 4mm. Each box assembly consists of 169 fuel rods which are arranged in a cylindrical shape, the outer diameter of each fuel rod is 8.6mm, the center of each fuel rod is provided with a center hole with the diameter of 1.9mm, the distance between the rods is 10mm, the thickness of a cladding is 0.55mm, helium is filled between each fuel pellet and the cladding, and the thickness is 0.15mm. Neutrons in the core with energy higher than 1MeV react with MA in a minor actinide transmutation zone to convert MA into short-lived nuclides or stable nuclides.
Fissionable fuel proliferation region 2: the fissionable fuel breeding field 2 consists of a 3-layered hexagonal module in which the MOX fuel module 132 cartridges, the control module 12 cartridges are housed. The fuel assembly structure and the fuel rod structure are the same as those of the minor actinide transmutation region 1. Fast neutrons can cause fissionable nuclides 238 U in MOX fuel to be fissionable nuclides 239 Pu in the fissionable fuel breeder region 2, so that the breeder of nuclear fuel is realized, and neutrons are provided for the transmutation region while the energy is produced.
Long life fission product transmutation zone 3: long life fission product transmutation zone 3 consists of a 2-layer hexagonal assembly containing fuel assembly 122 cartridges of UO 2 and LLFP mixtures, control assembly 6 cartridges. The fuel assembly height was 3.8m. As shown in FIG. 3, the spacing between the centers of the assemblies is 198mm, the gaps between the assemblies are 4mm, the wall thickness of the assemblies is 4mm, 2mm of the centers of the walls of the assemblies are graphite slowing layers, and each box assembly consists of 169 fuel rods and is in cylindrical arrangement. As shown in FIG. 4, the outer diameter of the fuel rod is 6.6mm, the center is provided with a center hole with the diameter of 1.6mm, the rod spacing is 10mm, helium is filled between the fuel pellet and the cladding, the thickness is 0.15mm, the thickness of the cladding is 1.55mm, and the 1mm of the cladding center is a graphite slowing layer. Neutrons entering long-life fission product transmutation zone 3, due to being farther from the core center, are mostly lower in neutron energy relative to the center, are moderated at the fuel assembly wall by a 2mm graphite moderation layer, and are moderated by a 1mm graphite moderation layer in the fuel rod cladding prior to contact with the fuel. In a word, neutrons are all slowed down by graphite before entering and exiting the fuel assembly and the fuel rod, and neutrons with lower energy are slowed down for a plurality of times to become low-energy neutrons, so that LLFP can be effectively transmuted, and the neutron utilization rate and the transmutation efficiency are improved.
Reflective layer region 4: the reflecting layer region 4 is composed of 1 layer of hexagonal reflecting layer components, the main material is T91 steel, and a zirconia/yttrium mixture is arranged in the reflecting material, so that neutrons leaked from the long-service-life fission product transmutation region 3 can be reflected for further utilization.
Shielding layer region 5: the shielding layer area 5 is composed of 2 layers of hexagonal shielding layer components, the shielding material is boron carbide, the structural material is T91 steel, neutrons leaking from the reflecting layer area 4 are mainly shielded, and irradiation damage of the reactor core to peripheral materials is reduced.
The rapid-heating mixed energy spectrum critical reactor core structure capable of simultaneously transmuting minor actinides and long-life fission products provided by the invention can effectively utilize neutrons in a region from a minor actinides transmutation region 1, a fissionable fuel proliferation region 2 to a long-life fission product transmutation region 3, improves transmutation rate and neutron utilization rate, realizes the function of simultaneously transmuting MA and LLFP, and adopts liquid metal as a cooling agent to carry out fission energy generated by a reactor core, thereby achieving the purpose of productivity.
Parts of the invention not described in detail are well known in the art.
While the foregoing describes illustrative embodiments of the present invention to facilitate an understanding of the present invention by those skilled in the art, it should be understood that the present invention is not limited to the scope of the embodiments, but is to be construed as protected by the accompanying claims insofar as various changes are within the spirit and scope of the present invention as defined and defined by the appended claims.
Claims (7)
1. A rapid thermal mixing energy spectrum critical core capable of simultaneously transmuting minor actinides and long-life fission products, characterized by: the reactor core is sequentially from the center to the outside: a minor actinide nuclear species transmutation zone (1), a fissionable fuel proliferation zone (2), a long-life fission product transmutation zone (3), a reflective layer zone (4) and a shielding layer zone (5); the minor actinide nuclide transmutation area (1), the fissionable fuel proliferation area (2) and the long-life fission product transmutation area (3) are all provided with control components; the minor actinide transmutation area (1) takes a mixture of MOX and MA as fuel, and high-energy neutrons of the reactor core transmute MA in the minor actinide transmutation area; the fissionable fuel breeder area (2) takes MOX as fuel, fast neutrons can cause fissionable nuclides 238 U to be fissionable nuclides 239 Pu finally, the breeder of nuclear fuel is realized, and partial neutrons can be used by a transmutation area; the long-life fission product transmutation area (3) takes a mixture of UO 2 and LLFP as fuel, neutrons entering the long-life fission product transmutation area (3) are far away from the center of a reactor core, and graphite layers are arranged in the fuel assembly wall and the fuel rod cladding, so that the long-life fission product transmutation area can be further slowed down into low-energy neutrons, most neutrons have lower energy relative to the center neutrons, LLFP can be effectively transmuted, the neutron utilization rate is improved, and the simultaneous transmutation of minor actinides and long-life fission products can be realized.
2. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the high-energy neutrons of the reactor core are transmuted into MA in a minor actinide nuclide transmutation area (1), the proliferation of nuclear fuel is realized in a fissionable fuel proliferation area (2), and the neutrons entering a long-service-life fission product transmutation area (3) are further slowed down into low-energy neutrons by a graphite layer in a fuel assembly wall and a fuel rod cladding due to being far away from the center of the reactor core, most neutrons have lower energy relative to the center neutrons, can be effectively transmuted LLFP, the utilization rate of neutrons is improved, the simultaneous transmutation of minor actinide nuclides and long-service-life fission products is realized, and the liquid metal is adopted as a cooling agent to carry out the fission energy generated by the reactor core, so that the purpose of capacity is achieved.
3. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the minor actinide nuclide transmutation area (1) takes a mixture of MOX and MA as fuel, wherein MA is extracted from cooled reactor spent fuel and comprises Np, am and Cm nuclides, and the nuclides undergo a fission reaction with fast neutrons to become fission products.
4. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the fissionable fuel proliferation area (2) takes MOX as fuel, is formed by mixing UO 2 and PuO 2, and fissionable nuclide 238 U is converted into fissionable nuclide 239 Pu after neutrons are captured, so that nuclear fuel proliferation is realized.
5. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the long-life fission product transmutation area (3) takes a mixture of UO 2 and LLFP as fuel, and LLFP is technetium-99 and iodine-129 extracted from cooled reactor spent fuel; a moderating layer is disposed within both the fuel assembly wall and the fuel rod cladding, the moderating material being graphite.
6. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the reflective layer region (4) is composed of a layer of reflective layer composition having a zirconia/yttria blend therein.
7. The rapid thermal mixing energy spectrum critical core for simultaneously transmuting minor actinides and long-life fission products of claim 1, wherein: the shielding layer area (5) is composed of two layers of shielding layer assemblies, and the shielding material is boron carbide.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810409760.6A CN108470589B (en) | 2018-05-02 | 2018-05-02 | Fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-service-life fission products |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810409760.6A CN108470589B (en) | 2018-05-02 | 2018-05-02 | Fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-service-life fission products |
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| Publication Number | Publication Date |
|---|---|
| CN108470589A CN108470589A (en) | 2018-08-31 |
| CN108470589B true CN108470589B (en) | 2024-05-17 |
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