WO2022167007A1 - Irradiation target for producing mo-99 isotope in heavy water reactor - Google Patents

Irradiation target for producing mo-99 isotope in heavy water reactor Download PDF

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WO2022167007A1
WO2022167007A1 PCT/CN2022/085054 CN2022085054W WO2022167007A1 WO 2022167007 A1 WO2022167007 A1 WO 2022167007A1 CN 2022085054 W CN2022085054 W CN 2022085054W WO 2022167007 A1 WO2022167007 A1 WO 2022167007A1
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enriched uranium
uranium
cladding
alloy
fuel
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PCT/CN2022/085054
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French (fr)
Chinese (zh)
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陈芙梁
卢俊强
周云清
韩宇
叶青
朱丽兵
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上海核工程研究设计院有限公司
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Publication of WO2022167007A1 publication Critical patent/WO2022167007A1/en

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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
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21K—TECHNIQUES FOR HANDLING PARTICLES OR IONISING RADIATION NOT OTHERWISE PROVIDED FOR; IRRADIATION DEVICES; GAMMA RAY OR X-RAY MICROSCOPES
    • G21K5/00—Irradiation devices
    • G21K5/08—Holders for targets or for other objects to be irradiated
    • 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
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • G21G2001/0036—Molybdenum
    • 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

Definitions

  • the invention relates to the technical field of fission nuclear reactors, in particular to an irradiation target for producing Mo-99 isotope in a heavy water reactor.
  • Nuclear medicine is an indispensable and important subject in medicine. It plays a special role in the diagnosis and treatment of human diseases and has developed rapidly in recent years.
  • 99m Tc can be combined with a variety of ligands to form a variety of organ and functional imaging agents, which can be used to diagnose various diseases and determine changes in the functional status of human organs. According to the data of Nature News & Comment, the number of clinical diagnoses using 99m Tc-related imaging technology reaches 30 million to 40 million person-times worldwide each year, accounting for 80% of all nuclear medicine applications.
  • the half-life of 99m Tc is very short, only 6.02 hours, and it usually needs to be decayed in real time from its parent isotope Mo-99, which has a half-life of 66 hours, where it is used.
  • Mo-99 is used to generate 99mTc , a molybdenum-technetium generator. So while the actual isotope used in a hospital or nuclear pharmacy is 99m Tc, the reactor produces and supplies Mo-99. According to estimates by NECSA (Nuclear Energy Corporation of South Africa), the market for Mo-99 isotopes exceeds $5 billion/year.
  • HEU high enriched uranium
  • the neutron absorption cross section is very small, generally only about 0.13 barnes.
  • the production of Mo-99 by the capture method has the disadvantage of low unit yield, and due to the Mo-98 carrier
  • the existence of Mo-99 produced has the inherent disadvantage of low specific activity, which will cause a large elution volume and a large generator volume, which is difficult to meet the medical requirements.
  • the target material used in the capture method is Mo-98, That is to say, in the selected fuel channel, the fuel bundle is replaced with a target that mainly contains Mo-98, and the target loses the function of the original fuel bundle to generate heat through the chain nuclear fission reaction to generate electricity. Nuclear power plants generate electricity.
  • a conventional fuel bundle is generally a cylindrical assembly composed of 37 fuel elements 1 welded with two Zr-4 material end plates 2 .
  • the fuel element 1 is mainly composed of a uranium-containing core 12, a cladding shell 11 made of Zr-4 material, and an end plug made of Zr-4 material.
  • the outer diameter of the cladding 11 is 13.1 mm
  • the inner diameter is 12.3 mm.
  • the uranium-containing core 12 adopts a UO 2 pellet with natural abundance, and the diameter of the natural abundance UO 2 pellet is 12.2 mm.
  • End plugs are welded to both ends of the cladding to seal the fuel element. The end plate and the fuel element end plug are also connected by welding.
  • a spacer is welded between each fuel element, and the space between the fuel elements can be maintained by the contact of the spacer between the adjacent fuel elements after the fuel element is loaded into the bundle.
  • additional support gaskets 3 are provided at both ends and the middle near the periphery to maintain the gap between the fuel bundle and the pressure pipe.
  • UO 2 pellets are natural abundance ceramic UO 2 powders that are compressed and sintered at high temperature to form a cylindrical shape.
  • the abundance of 235 U in natural uranium is 0.71 wt%.
  • 235 U is prone to fission reaction under neutron irradiation, and the distribution of its fission products forms two humps with atomic weights around 100 and 135.
  • Mo-99 is just at one of the hump positions, and its fission product share is as high as 6.13 %.
  • conventional fuel bundles use natural uranium.
  • the content of 235 U in natural uranium is too low, and the efficiency of directly extracting Mo-99 from the fission products of conventional fuel bundles is too low.
  • the present invention provides an irradiation target for producing Mo-99 isotope in a heavy water reactor, which can efficiently produce Mo-99 and facilitate the extraction of the produced Mo-99 in the later stage, and at the same time can maximize the production of Mo-99. reduce the impact on nuclear power generation.
  • the irradiation target for producing Mo-99 isotope in a heavy water reactor of the present invention includes: a plurality of fuel elements including a cladding, a uranium-containing core and an end plug, the end of the cladding has a filling opening; the The end plug is covered on the filling opening at the end of the cladding, and is sealedly connected with the cladding, and the uranium-containing core is filled in the sealed chamber formed by the end plug and the cladding; a plate, which is arranged at both ends of the fuel element and is fixedly connected with a plurality of the fuel elements; wherein, the uranium-containing core of at least one of the fuel elements includes an enriched uranium core, and the enriched uranium core It contains enriched uranium fuel, and the enrichment degree of 235 U of the enriched uranium fuel ranges from 6.0wt% to 20.0wt%.
  • the enriched uranium fuel is UO 2 , UN, UC, U 3 Si 2 , U metal, U-Zr alloy or U-Al alloy or their combination with industrially pure zirconium, zirconium alloy, industrially pure aluminum, aluminum alloy, Any combination of industrial pure molybdenum, molybdenum alloy, industrial pure niobium, niobium alloy, stainless steel, nickel alloy, silicon carbide.
  • the remaining materials in the fuel element except the enriched uranium fuel are materials with a thermal neutron macroscopic absorption cross section of less than 10 barnes.
  • the material with a macroscopic thermal neutron absorption cross-section of less than 10 barnes includes the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide or Depleted uranium.
  • the enriched uranium core is a solid enriched uranium rod, enriched uranium pellet or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core is 15-20wt%; the The outer diameter of the cladding shell is 10.0-14.0mm, and the inner diameter thereof is 0.5-7.0mm; the cladding shell and the end plug respectively adopt any one of the following core-grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, Aluminum alloy, nickel-based alloy, silicon carbide.
  • the uranium-containing core includes an intermediate thick-walled tube with a hole opening along the central axis, an enriched uranium core embedded in the through hole of the intermediate thick-walled tube, and the enriched uranium core is a solid core.
  • the enriched uranium core is formed by coating the outer wall of a cylindrical support tube with enriched uranium coating;
  • the support tube and the cladding are respectively made of any one of the following nuclear-grade materials: zirconium alloy , niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide;
  • the outer diameter of the cladding shell is 10.0-14.0mm, the inner diameter is 9.0-13.0mm, the outer diameter of the support tube is 9.0-13.0mm, The inner diameter is 7.0-12.0 mm, and the thickness of the enriched uranium coating is 50-500 ⁇ m.
  • the uranium-containing cores are enriched uranium cores and filling pellets which are sequentially interleaved and embedded in the cladding along the length direction of the cladding, and the enriched uranium cores are enriched uranium pellets;
  • the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium pellets is 6-20wt%;
  • the filling pellets and the end plugs are respectively made of any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy Alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide; the ratio of the enriched uranium pellet stacking length to the filling pellet stacking length is 1:50-1:10.
  • the irradiation target for producing Mo-99 isotope in the heavy water reactor of the present invention makes full use of the characteristics of the heavy water reactor's non-stop refueling, and can use the existing reactor to continuously produce Mo-99 with a short half-life period, and it is not necessary to specially build a new one.
  • the irradiation facility in China uses enriched uranium to replace the natural abundance UO 2 pellets, and aggregates 235 U originally evenly distributed in the natural abundance UO 2 pellets to produce Mo-99 with high efficiency and good quality, that is, specific activity
  • the irradiation target of the present invention is used to produce Mo-99, and at the same time, the influence on the power generation of the nuclear power plant can be reduced to the greatest extent.
  • FIG. 1 is a schematic perspective view of a conventional conventional fuel bundle using natural uranium.
  • FIG. 2 is a cross-sectional view of the conventional fuel element shown in FIG. 1 .
  • Fig. 3 is a fission product yield-mass number curve diagram of 235 U fissioned under neutron irradiation.
  • FIG. 4 is a cross-sectional view of a fuel element comprising a uranium-containing core and a cladding in accordance with an embodiment of the present invention.
  • FIG. 5 is a cross-sectional view of a fuel element comprising a uranium-containing core, an intermediate thick-walled tube, and a cladding, in accordance with an embodiment of the present invention.
  • FIG. 6 is a cross-sectional view of a fuel element comprising an enriched uranium coating, a support tube, and a cladding in one embodiment of the present invention.
  • FIG. 7 is a longitudinal cross-sectional view of a fuel element comprising enriched uranium pellets, packed pellets, and cladding in accordance with an embodiment of the present invention.
  • FIG. 8 is an enlarged cross-sectional view taken along the line A-A of FIG. 7 .
  • an irradiation target for the production of Mo-99 isotope in a heavy water reactor includes: a fuel element 1, which includes a cladding 11, a uranium-containing core 14 and an end plug 16, the end of the cladding 11 has Filling opening; the end plug 16 is covered on the filling opening at the end of the cladding 11, and is sealed with the cladding 11, and the uranium-containing core 14 is filled in the sealed chamber formed by the end plug 16 and the cladding 11; the end plate 2, It is arranged at both ends of the fuel element 1 and is fixedly connected with several fuel elements 1; wherein, at least one uranium-containing core 14 in the fuel element 1 is provided with enriched uranium fuel, and the enrichment degree of 235 U of the enriched uranium fuel is 6.0wt. % ⁇ 20.0wt%.
  • the enrichment degree of 235 U of the enriched uranium fuel is between 15.0 wt % and 20.0 wt
  • the enriched uranium fuel is UO 2 , UN, UC, U 3 Si 2 , U metal, U-Zr alloy or U-Al alloy or their combination with industrially pure zirconium, zirconium alloy, industrially pure aluminum, aluminum alloy, industrially pure Any combination of molybdenum, molybdenum alloy, industrial pure niobium, niobium alloy, stainless steel, nickel alloy, silicon carbide.
  • the remaining materials in the fuel element 1 except for the enriched uranium fuel are all materials with a macroscopic absorption cross section of thermal neutrons less than 10 barnes.
  • the material with a macroscopic thermal neutron absorption cross section of less than 10 barnes includes the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, alumina, beryllium oxide or depleted uranium.
  • the uranium-containing core 14 in this example includes an enriched uranium core 15 using solid enriched uranium rods or enriched uranium pellets or enriched uranium powder, and 235 U enriched uranium fuel in the enriched uranium core 15
  • concentration is 15-20wt%;
  • the outer diameter of the cladding shell 11 is 10.0-14.0mm, and the inner diameter thereof is 0.5-7.0mm; , niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide.
  • the uranium-containing core 14 includes the enriched uranium core 15 formed by using a plurality of enriched uranium pellets with a 235 U enrichment of 19.5wt% UO 2 stacked in sequence along the axial direction of the cladding 11.
  • the cladding 11 A Zr-4 thick-walled tube with a wall thickness of 5.55mm was used.
  • the enriched uranium pellets have a diameter of 2 mm and are tightly embedded in the cladding 11 .
  • the enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation.
  • the outermost circle of 18 fuel elements 1 of the irradiation target adopts the fuel elements 1 shown in FIG. 4
  • the inner three circles of 19 fuel elements 1 adopt the conventional fuel elements shown in FIG. 2
  • a single irradiation target is produced
  • the Mo-99 isotope is at 1000 Curies, that is, above the 6-day mark (ie, the amount of Mo-99 left after decaying for more than 6 days).
  • the fuel element 1 containing the enriched uranium material is placed on the outer ring of the target, because the enriched uranium material needs to be used to extract Mo-99 in the subsequent steps, and it is arranged on the outer ring of the irradiation target beam to facilitate disassembly; In the outer ring, the self-shielding effect is small, and the nuclear reaction is more likely to occur.
  • the enriched uranium pellets in this example can also be replaced with enriched uranium powder, that is, the enriched uranium powder is put into the cladding 11 for compaction. It is also possible to directly replace several enriched uranium pellets with a whole UO 2 enriched uranium rod.
  • the uranium-containing core 14 in this example includes a middle thick-walled tube 12 with a hole along the central axis, a solid enriched uranium rod or a plurality of solid enriched uranium rods embedded in the through hole of the middle thick-walled tube 12 as the enriched uranium core 15.
  • the enriched uranium pellet or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core 15 is 15-20 wt%;
  • the intermediate thick-walled tube adopts any one of the following nuclear grade materials: zirconium alloy, Niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide;
  • the materials of the cladding 11 and the end plug 16 are Zr-4 respectively;
  • the outer diameter of the cladding 11 is 10.0-14.0mm, and the wall thickness is 0.3-1.0 mm;
  • the outer diameter of the middle thick-walled tube 12 is 9.0-13.0 mm, and the wall thickness is 1.0-6.25 mm;
  • the diameter of the enriched uranium rod or pellet or powder is between 0.5-7.0 mm.
  • the uranium-containing core 14 includes a number of enriched uranium pellets with 235 U enrichment of 15.0 wt% and a diameter of 2.7 mm as the enriched uranium core 15 , which are loaded into Zr- 4 material into the middle thick-walled tube 12, and then put the middle thick-walled tube 12 into the cladding 11 of the thin-walled Zr-4 material with a thickness of 0.4 mm.
  • the outer diameter of the middle thick-walled tube 12 is 12.2 mm, and the inner diameter is 4.75 mm.
  • the enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation.
  • the 18 elements in the outermost circle of the irradiation target are the fuel elements 1 shown in FIG. 5
  • the 19 fuel elements 1 in the inner three circles are the conventional fuel elements shown in FIG. 2 .
  • a single irradiation target is produced.
  • the Mo-99 isotope is above 1000 Curies.
  • the enriched uranium pellets in this example can also be replaced with enriched uranium powder, that is, the enriched uranium powder is put into the cladding 11 for compaction. It is also possible to directly replace several enriched uranium pellets with a whole UO 2 enriched uranium rod.
  • the enriched uranium core 15 is formed by coating the outer wall of a cylindrical support tube with enriched uranium coating;
  • the support tube 13 and the cladding 11 are respectively made of any one of the following nuclear-grade materials : zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide;
  • the outer diameter of the cladding 11 is 10.0-14.0mm, the inner diameter is 9.0-13.0mm, the outer diameter of the support tube is 9.0-13.0mm, The inner diameter is 7.0 to 12.0 mm, and the thickness of the enriched uranium coating is 50 to 500 ⁇ m.
  • the thickness of the enriched uranium coating takes into account the feasibility of enriched uranium coatings and coatings with different 235 U enrichment degrees. If the enrichment degree of 235 U is high and the total amount of 235 U remains unchanged, then the The amount is less, and vice versa; in addition, the coating is too thin or too thick, which is not conducive to manufacturing.
  • the enriched uranium core 15 is formed by coating the outer surface of the support tube 13 with an outer diameter of 11.8 mm and an inner diameter of 9.8 mm with UO 2 with a 235 U enrichment of 10.0 wt% to form an enriched uranium coating with a thickness of 160 ⁇ m.
  • the support tube 13 is made of stainless steel.
  • a cladding 11 made of Zr-4 material with an inner diameter of 12.3 mm is added to the outside of the enriched uranium core 15 to form a "sandwich" structure.
  • the enriched uranium coating of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation.
  • the 18 fuel elements in the outermost circle of the irradiation target are the fuel elements 1 shown in FIG. 6
  • the 19 fuel elements 1 in the inner three circles are the conventional fuel elements shown in FIG. 2 , and a single irradiation target is produced.
  • the Mo-99 isotope is above 1000 Curies.
  • the uranium-containing cores 14 in the cladding 11 are formed by interlacing the enriched uranium cores 15 and the filling pellets 17 made of beryllium oxide; the enriched uranium core 15 is made of enriched uranium pellets.
  • the enrichment degree of 235 U of the enriched uranium fuel in the uranium pellet is 6-20wt%; the filling pellet 17 and the end plug 16 are respectively made of any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel , aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide; the ratio of the stacking length of enriched uranium pellets to the stacking length of filled pellets 17 is 1:50 to 1:10
  • the uranium-containing core 14 is formed by interlacing the enriched uranium core 15 with UO 2 with a 235 U enrichment of 6.0 wt % and the filled pellets 17 made of beryllium oxide at intervals.
  • the enriched uranium cores 15 are UO 2 enriched uranium pellets
  • the beryllium oxide filled pellets 17 are all 12.2 mm in diameter
  • the ratio of the stacking lengths of the UO 2 enriched uranium pellets to the beryllium oxide filled pellets 17 is 1:10.
  • the enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation.
  • the 18 fuel elements in the outermost circle of the irradiation target use the fuel elements shown in Figures 7 and 8, and the 19 fuel elements in the inner three circles use the conventional fuel elements shown in Figure 2.
  • the core of the design principle of the present invention is: considering the neutron irradiation of enriched uranium, after the fission reaction occurs, separation of Mo-99 from the target by radiochemical means is the most efficient production means. Therefore, the technical solution of the present invention is to replace part of the UO 2 uranium-containing core 14 with natural 235 U abundance in at least one fuel element 1 with enriched uranium material, so that the amount of 235 U in the irradiation target of the present application is the same as the current one.
  • the amount of 235 U in conventional fuel bundles is roughly the same, so that the nuclear properties and thermal performance of the fuel bundle substitutes are basically unchanged, thereby ensuring the safe and economical power generation of nuclear power plants.

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Abstract

The present invention provides an irradiation target for producing a Mo-99 isotope in a heavy water reactor, comprising: a plurality of fuel elements, each comprising a cladding, a uranium-containing core, and an end plug. An end part of the cladding is provided with a filling opening. The end plug covers the filling opening at the end part of the cladding, and is in sealing connection with the cladding. The uranium-containing core is filled in a sealed cavity formed by the end plug and the cladding. A plurality of fuel elements are provided. End plates are arranged at both ends of the fuel elements and are fixedly connected to the plurality of fuel elements. The uranium-containing core of at least one of the fuel elements is an uranium-containing core provided with a rich uranium fuel, and the 235 U enrichment degree of enriched uranium fuel is 6.0 wt% - 20.0 wt%. By means of the present invention, existing reactors may be utilized for non-stop production of Mo-99 having a short half-life. By using enriched uranium to produce Mo-99, the efficiency is high and the quality is good. Meanwhile, effects on power generation of a nuclear power plant can be reduced to a maximum extent.

Description

在重水堆中生产Mo-99同位素的辐照靶件Irradiation targets for the production of Mo-99 isotopes in heavy water reactors 技术领域technical field
本发明涉及裂变型核反应器技术领域，具体地说是一种在重水堆中生产Mo-99同位素的辐照靶件。The invention relates to the technical field of fission nuclear reactors, in particular to an irradiation target for producing Mo-99 isotope in a heavy water reactor.
背景技术Background technique
核医学是医学中不可缺少的重要学科，它在人体疾病的诊断和治疗方面都发挥着特殊作用，近年来得到了迅速的发展。 99mTc可与多种配体结合形成多种脏器和功能显像剂，用于诊断各种疾病以及判断人体脏器功能状况变化等。根据Nature News&Comment的数据，全球每年使用 99mTc相关显像技术进行的临床诊断达3000万～4000万人次，占全部核医学应用的80％。 Nuclear medicine is an indispensable and important subject in medicine. It plays a special role in the diagnosis and treatment of human diseases and has developed rapidly in recent years. 99m Tc can be combined with a variety of ligands to form a variety of organ and functional imaging agents, which can be used to diagnose various diseases and determine changes in the functional status of human organs. According to the data of Nature News & Comment, the number of clinical diagnoses using 99m Tc-related imaging technology reaches 30 million to 40 million person-times worldwide each year, accounting for 80% of all nuclear medicine applications.
99mTc的半衰期很短，只有6.02小时，通常需要在使用的地方实时由其半衰期为66小时的母体同位素Mo-99衰变得到。使用Mo-99产生 99mTc的装置即钼-锝发生器。因此，尽管医院或核药房实际使用的同位素为 99mTc，但是反应堆生产和供应的是Mo-99。根据NECSA(Nuclear Energy Corporation of South Africa)的估计，Mo-99同位素的市场超过50亿美元/年。 The half-life of 99m Tc is very short, only 6.02 hours, and it usually needs to be decayed in real time from its parent isotope Mo-99, which has a half-life of 66 hours, where it is used. Mo-99 is used to generate 99mTc , a molybdenum-technetium generator. So while the actual isotope used in a hospital or nuclear pharmacy is 99m Tc, the reactor produces and supplies Mo-99. According to estimates by NECSA (Nuclear Energy Corporation of South Africa), the market for Mo-99 isotopes exceeds $5 billion/year.
近年全球Mo-99同位素主要由加拿大MDS Nordion、荷兰Mallinckrodt-Covidien、比利时IRE(Institute National des Raioéléments)、南非NTP(Nuclear Technology Products)、澳大利亚ANSTO(the Australian Nuclear Science and Technology Organisation) 等五个全球性供应商供应。这些供应商使用的研究堆或试验堆多建于上世纪五六十年代，老化严重，预计在2016～2030年间陆续关闭。此外，他们大多采用 235U富集度90％以上的高浓铀(high enriched uranium,HEU)靶件。由于HEU可用于核武器及核爆装置制备，而被认为是高风险核材料。为减少全球威胁国际上倡导从HEU向低浓铀(low enriched uranium,LEU)进行转换。 In recent years, the global Mo-99 isotope is mainly composed of five global isotopes including MDS Nordion in Canada, Mallinckrodt-Covidien in the Netherlands, IRE (Institute National des Raioéléments) in Belgium, NTP (Nuclear Technology Products) in South Africa, and ANSTO (the Australian Nuclear Science and Technology Organisation) in Australia. Supplier supply. Most of the research reactors or test reactors used by these suppliers were built in the 1950s and 1960s, are seriously aging, and are expected to be closed between 2016 and 2030. In addition, most of them use high enriched uranium (HEU) targets with 235 U enrichment over 90%. Because HEU can be used in the preparation of nuclear weapons and nuclear explosive devices, it is considered to be a high-risk nuclear material. Conversion from HEU to low enriched uranium (LEU) is advocated internationally to reduce global threats.
相比HEU靶件，利用LEU生产Mo-99会导致产品产额的降低，生产成本增加近20％。这种转变将给全球Mo-99市场供给带来一定影响。因此，世界各国一方面全面推进辐照装置建设项目的开展，一方面不断寻求获得Mo-99的新途径、新方法。加拿大BWTX公司(BWX Technologies,Inc.)在CN111066095A(2020.04.24)和CN110462750A(2019.11.15)中介绍了在重水堆中通过俘获法生产Mo-99的方法。由于Mo-99的半衰期很短，生成后就要尽快分离提取使用，重水堆可以在线换料，即不停堆换料，对于生产这种短衰变期同位素具有天然的优势。Compared with the HEU target, the use of LEU to produce Mo-99 results in a decrease in product yield and an increase in production cost by nearly 20%. This transition will have a certain impact on the supply of the global Mo-99 market. Therefore, all countries in the world are on the one hand comprehensively promoting the development of the irradiation device construction project, and on the other hand, they are constantly seeking new ways and methods to obtain Mo-99. Canadian BWTX company (BWX Technologies, Inc.) introduced the method of producing Mo-99 by capture method in heavy water reactors in CN111066095A (2020.04.24) and CN110462750A (2019.11.15). Due to the short half-life of Mo-99, it must be separated and extracted as soon as possible after it is generated. The heavy water reactor can be refueled online, that is, it can be refueled continuously, which has natural advantages for the production of this short decay period isotope.
但是由于俘获法生产Mo-99中使用的是Mo-98，其中子吸收截面很小，一般只有约0.13靶恩，使用俘获法生产Mo-99具有单位产量低的缺点，并且由于Mo-98载体的存在，生产出来的Mo-99具有比活度低的固有缺点，会造成淋洗体积大、发生器体积大，难以满足医用的要求，此外，俘获法所使用的靶材是Mo-98，就是说在选定的燃料通道内把燃料棒束替换为主要包含Mo-98的靶件，此靶件就失去了原来燃料棒束通过链式核裂变反应产生热量用来发电的作用，因此影响核电厂发电。However, since Mo-98 is used in the production of Mo-99 by the capture method, the neutron absorption cross section is very small, generally only about 0.13 barnes. The production of Mo-99 by the capture method has the disadvantage of low unit yield, and due to the Mo-98 carrier The existence of Mo-99 produced has the inherent disadvantage of low specific activity, which will cause a large elution volume and a large generator volume, which is difficult to meet the medical requirements. In addition, the target material used in the capture method is Mo-98, That is to say, in the selected fuel channel, the fuel bundle is replaced with a target that mainly contains Mo-98, and the target loses the function of the original fuel bundle to generate heat through the chain nuclear fission reaction to generate electricity. Nuclear power plants generate electricity.
参见图1，常规的燃料棒束一般由37根燃料元件1与两块Zr-4材质的端板2焊接组成的圆柱状的组件。参见图2，燃料元件1主要由含铀芯子12、Zr-4材质的包壳11和Zr-4材质的端塞组成。其中，包壳11的外 径13.1mm，内径12.3mm，含铀芯子12采用天然丰度的UO 2芯块，天然丰度的UO 2芯块直径12.2mm。将端塞焊接在包壳的两端以密封燃料元件。端板与燃料元件端塞之间也是通过焊接连接。每根燃料元件中间都焊接有定位垫片，燃料元件装入棒束后相邻燃料元件的定位垫片接触可以保持燃料元件之间的间隙。对于***燃料元件，在靠近***的两端和中部额外还设置支承垫片3，用来保持燃料棒束与压力管的间隙。 Referring to FIG. 1 , a conventional fuel bundle is generally a cylindrical assembly composed of 37 fuel elements 1 welded with two Zr-4 material end plates 2 . Referring to FIG. 2, the fuel element 1 is mainly composed of a uranium-containing core 12, a cladding shell 11 made of Zr-4 material, and an end plug made of Zr-4 material. Among them, the outer diameter of the cladding 11 is 13.1 mm, and the inner diameter is 12.3 mm. The uranium-containing core 12 adopts a UO 2 pellet with natural abundance, and the diameter of the natural abundance UO 2 pellet is 12.2 mm. End plugs are welded to both ends of the cladding to seal the fuel element. The end plate and the fuel element end plug are also connected by welding. A spacer is welded between each fuel element, and the space between the fuel elements can be maintained by the contact of the spacer between the adjacent fuel elements after the fuel element is loaded into the bundle. For the peripheral fuel element, additional support gaskets 3 are provided at both ends and the middle near the periphery to maintain the gap between the fuel bundle and the pressure pipe.
常规的燃料棒束中UO 2芯块为天然丰度陶瓷UO 2粉末经压制成型、高温烧结制成圆柱形。天然铀中 235U的丰度为0.71wt％。 235U在中子照射下易发生裂变反应，其裂变产物的分布形成了原子量在100和135附近的两个驼峰，参见图3，Mo-99刚好处于其中一个驼峰位置，其裂变产物份额高达6.13％。但是常规的燃料棒束使用的是天然铀，天然铀中 235U的含量太低，直接从常规的燃料棒束裂变产物中提取Mo-99效率太低。 In conventional fuel bundles, UO 2 pellets are natural abundance ceramic UO 2 powders that are compressed and sintered at high temperature to form a cylindrical shape. The abundance of 235 U in natural uranium is 0.71 wt%. 235 U is prone to fission reaction under neutron irradiation, and the distribution of its fission products forms two humps with atomic weights around 100 and 135. See Figure 3, Mo-99 is just at one of the hump positions, and its fission product share is as high as 6.13 %. However, conventional fuel bundles use natural uranium. The content of 235 U in natural uranium is too low, and the efficiency of directly extracting Mo-99 from the fission products of conventional fuel bundles is too low.
发明内容SUMMARY OF THE INVENTION
本发明为了克服以上技术问题，提供一种在重水堆中生产Mo-99同位素的辐照靶件，可以高效的生产Mo-99并且方便后期对生产出来的Mo-99进行提取，同时可最大程度上减少对核电厂发电的影响。In order to overcome the above technical problems, the present invention provides an irradiation target for producing Mo-99 isotope in a heavy water reactor, which can efficiently produce Mo-99 and facilitate the extraction of the produced Mo-99 in the later stage, and at the same time can maximize the production of Mo-99. reduce the impact on nuclear power generation.
本发明的在重水堆中生产Mo-99同位素的辐照靶件，包括：若干根燃料元件，其包括包壳、含铀芯子和端塞，所述包壳端部具有填充开口；所述端塞盖设于所述包壳端部的所述填充开口，并与所述包壳密封连接，所述含铀芯子填充于所述端塞与所述包壳形成的密封腔室内；端板，其设置于所述燃料元件两端，与若干所述燃料元件固定连接；其中，所述燃料元件中至少有一根的所述含铀芯子包含浓铀芯子，所述浓铀芯子包含浓铀燃料，浓铀燃料的 235U富集度在6.0wt％～20.0wt％。 The irradiation target for producing Mo-99 isotope in a heavy water reactor of the present invention includes: a plurality of fuel elements including a cladding, a uranium-containing core and an end plug, the end of the cladding has a filling opening; the The end plug is covered on the filling opening at the end of the cladding, and is sealedly connected with the cladding, and the uranium-containing core is filled in the sealed chamber formed by the end plug and the cladding; a plate, which is arranged at both ends of the fuel element and is fixedly connected with a plurality of the fuel elements; wherein, the uranium-containing core of at least one of the fuel elements includes an enriched uranium core, and the enriched uranium core It contains enriched uranium fuel, and the enrichment degree of 235 U of the enriched uranium fuel ranges from 6.0wt% to 20.0wt%.
优选地，所述浓铀燃料为UO 2、UN、UC、U 3Si 2、U金属、U-Zr合金或U-Al合金或它们与工业纯锆、锆合金、工业纯铝、铝合金、工业纯钼、钼合金、工业纯铌、铌合金、不锈钢、镍合金、碳化硅的任意组合。 Preferably, the enriched uranium fuel is UO 2 , UN, UC, U 3 Si 2 , U metal, U-Zr alloy or U-Al alloy or their combination with industrially pure zirconium, zirconium alloy, industrially pure aluminum, aluminum alloy, Any combination of industrial pure molybdenum, molybdenum alloy, industrial pure niobium, niobium alloy, stainless steel, nickel alloy, silicon carbide.
优选地，所述燃料元件中除所述浓铀燃料外的其余材料均采用热中子宏观吸收截面小于10靶恩的材料。Preferably, the remaining materials in the fuel element except the enriched uranium fuel are materials with a thermal neutron macroscopic absorption cross section of less than 10 barnes.
优选地，所述热中子宏观吸收截面小于10靶恩的材料包括如下核级材料：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍或贫铀。Preferably, the material with a macroscopic thermal neutron absorption cross-section of less than 10 barnes includes the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide or Depleted uranium.
优选地，所述浓铀芯子采用实心的浓铀棒或浓铀芯块或浓铀粉体；所述浓铀芯子中浓铀燃料的 235U富集度为15～20wt％；所述包壳的外径为10.0～14.0mm，其内径为0.5～7.0mm；所述包壳、端塞分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅。 Preferably, the enriched uranium core is a solid enriched uranium rod, enriched uranium pellet or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core is 15-20wt%; the The outer diameter of the cladding shell is 10.0-14.0mm, and the inner diameter thereof is 0.5-7.0mm; the cladding shell and the end plug respectively adopt any one of the following core-grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, Aluminum alloy, nickel-based alloy, silicon carbide.
优选地，所述含铀芯子包括沿中心轴线开通孔的中间厚壁管、嵌设在所述中间厚壁管的所述通孔内的浓铀芯子，所述浓铀芯子采用实心浓铀棒或若干浓铀芯块或浓铀粉体；所述浓铀芯子中浓铀燃料的 235U富集度为15～20wt％；所述中间厚壁管采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；所述包壳及端塞的材料分别采用Zr-4；所述包壳外径为10.0～14.0mm，壁厚为0.3～1.0mm；所述中间厚壁管外径为9.0～13.0mm，壁厚为1.0～6.25mm；所述浓铀棒或浓铀芯块或浓铀粉体直径在0.5～7.0mm之间。 Preferably, the uranium-containing core includes an intermediate thick-walled tube with a hole opening along the central axis, an enriched uranium core embedded in the through hole of the intermediate thick-walled tube, and the enriched uranium core is a solid core. The enriched uranium rod or several enriched uranium pellets or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core is 15-20wt%; the middle thick-walled tube is made of the following nuclear grade materials. Any one of: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide; the materials of the cladding shell and the end plug are respectively Zr-4; the outer diameter of the cladding shell is 10.0～ 14.0mm, the wall thickness is 0.3-1.0mm; the outer diameter of the middle thick-walled tube is 9.0-13.0mm, and the wall thickness is 1.0-6.25mm; the diameter of the enriched uranium rod or enriched uranium pellet or enriched uranium powder is Between 0.5 and 7.0mm.
优选地，所述浓铀芯子为在圆筒状的支撑管的外壁涂覆浓铀涂层而成；所述支撑管、包壳分别采用包括如下核级材料中的任一种：锆合金、 铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；所述包壳外径为10.0～14.0mm、内径为9.0～13.0mm，所述支撑管外径为9.0～13.0mm、内径为7.0～12.0mm，所述浓铀涂层厚度为50～500μm。Preferably, the enriched uranium core is formed by coating the outer wall of a cylindrical support tube with enriched uranium coating; the support tube and the cladding are respectively made of any one of the following nuclear-grade materials: zirconium alloy , niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide; the outer diameter of the cladding shell is 10.0-14.0mm, the inner diameter is 9.0-13.0mm, the outer diameter of the support tube is 9.0-13.0mm, The inner diameter is 7.0-12.0 mm, and the thickness of the enriched uranium coating is 50-500 μm.
优选地，所述含铀芯子为沿包壳的长度方向依次交错嵌设在其内的采用浓铀燃料的浓铀芯子和填充芯块，所述浓铀芯子采用浓铀芯块；所述浓铀芯块中浓铀燃料的 235U富集度为6～20wt％；所述填充芯块、端塞分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍；所述浓铀芯块堆积长度与填充芯块堆积长度的比值为1:50～1:10。 Preferably, the uranium-containing cores are enriched uranium cores and filling pellets which are sequentially interleaved and embedded in the cladding along the length direction of the cladding, and the enriched uranium cores are enriched uranium pellets; The enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium pellets is 6-20wt%; the filling pellets and the end plugs are respectively made of any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy Alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide; the ratio of the enriched uranium pellet stacking length to the filling pellet stacking length is 1:50-1:10.
本发明的在重水堆中生产Mo-99同位素的辐照靶件，充分利用重水堆不停堆换料的特点，可以利用现有反应堆不间断的生产短半衰期的Mo-99，不必专门建设新的辐照设施，使用浓铀来替代天然丰度UO 2芯块，将原本均匀分布在天然丰度UO 2芯块中的 235U聚集起来，生产Mo-99效率高、品质好，即比活度高，使用本发明涉及的辐照靶件生产Mo-99的同时可最大程度上减少对核电厂发电的影响。 The irradiation target for producing Mo-99 isotope in the heavy water reactor of the present invention makes full use of the characteristics of the heavy water reactor's non-stop refueling, and can use the existing reactor to continuously produce Mo-99 with a short half-life period, and it is not necessary to specially build a new one. The irradiation facility in China uses enriched uranium to replace the natural abundance UO 2 pellets, and aggregates 235 U originally evenly distributed in the natural abundance UO 2 pellets to produce Mo-99 with high efficiency and good quality, that is, specific activity The irradiation target of the present invention is used to produce Mo-99, and at the same time, the influence on the power generation of the nuclear power plant can be reduced to the greatest extent.
附图说明Description of drawings
为了更清楚地说明本申请实施例的技术方案，下面将对本申请实施例中所需要使用的附图作简单地介绍，显而易见地，下面所描述的附图仅仅是本申请的一些实施例，对于本领域普通技术人员来讲，在不付出创造性劳动的前提下，还可以根据附图获得其他的附图。In order to explain the technical solutions of the embodiments of the present application more clearly, the following briefly introduces the drawings that need to be used in the embodiments of the present application. Obviously, the drawings described below are only some embodiments of the present application. For those of ordinary skill in the art, other drawings can also be obtained according to the drawings without any creative effort.
图1为现有采用天然铀的常规燃料棒束的立体示意图。FIG. 1 is a schematic perspective view of a conventional conventional fuel bundle using natural uranium.
图2为图1中所示常规燃料元件的截面图。FIG. 2 is a cross-sectional view of the conventional fuel element shown in FIG. 1 .
图3为 235U在中子照射下发生裂变后的裂变产物产额-质量数曲线图。 Fig. 3 is a fission product yield-mass number curve diagram of 235 U fissioned under neutron irradiation.
图4为本发明一实施例中包含含铀芯子和包壳的燃料元件的横截面图。4 is a cross-sectional view of a fuel element comprising a uranium-containing core and a cladding in accordance with an embodiment of the present invention.
图5为本发明一实施例中包含含铀芯子、中间厚壁管和包壳的燃料元件的横截面图。5 is a cross-sectional view of a fuel element comprising a uranium-containing core, an intermediate thick-walled tube, and a cladding, in accordance with an embodiment of the present invention.
图6为本发明一实施例中包含浓铀涂层、支撑管和包壳的燃料元件的横截面图。6 is a cross-sectional view of a fuel element comprising an enriched uranium coating, a support tube, and a cladding in one embodiment of the present invention.
图7为本发明一实施例中包含浓铀芯块、填充芯块和包壳的燃料元件的纵截面图。7 is a longitudinal cross-sectional view of a fuel element comprising enriched uranium pellets, packed pellets, and cladding in accordance with an embodiment of the present invention.
图8为图7的A-A向剖视放大图。FIG. 8 is an enlarged cross-sectional view taken along the line A-A of FIG. 7 .
在附图中，附图并未按照实际的比例绘制。In the drawings, the figures are not drawn to actual scale.
标记说明：Tag Description:
1-燃料元件1 - Fuel element
11-包壳11 - cladding
12-中间厚壁管12-Intermediate thick wall pipe
13-支撑管13-Support tube
14-含铀芯子14 - Uranium-containing core
15-浓铀芯子15-enriched uranium core
16-端塞16-end plug
17-填充芯块17 - Fill the pellets
2-端板2-end plate
3-支承垫片3-Support gasket
具体实施方式Detailed ways
下面结合附图和实施例对本申请的实施方式作进一步详细描述。以下实施例的详细描述和附图用于示例性地说明本申请的原理，但不能用来限制本申请的范围，即本申请不限于所描述的实施例。The embodiments of the present application will be described in further detail below with reference to the accompanying drawings and examples. The following detailed description of the embodiments and the accompanying drawings are used to illustrate the principles of the present application by way of example, but should not be used to limit the scope of the present application, that is, the present application is not limited to the described embodiments.
在本申请的描述中，需要说明的是，除非另有说明，“多个”的含义是两个以上；术语“上”、“下”、“左”、“右”、“内”、“外”等指示的方位或位置关系仅是为了便于描述本申请和简化描述，而不是指示或暗示所指的装置或元件必须具有特定的方位、以特定的方位构造和操作，因此不能理解为对本申请的限制。此外，术语“第一”、“第二”、“第三”等仅用于描述目的，而不能理解为指示或暗示相对重要性。In the description of this application, it should be noted that, unless otherwise specified, the meaning of "plurality" is two or more; the terms "upper", "lower", "left", "right", "inner", " The orientation or positional relationship indicated by "outside" is only for the convenience of describing the present application and simplifying the description, rather than indicating or implying that the indicated device or element must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be construed as a reference to the present application. Application restrictions. Furthermore, the terms "first," "second," "third," etc. are used for descriptive purposes only and should not be construed to indicate or imply relative importance.
下述描述中出现的方位词均为图中示出的方向，并不是对本申请的具体结构进行限定。在本申请的描述中，还需要说明的是，除非另有明确的规定和限定，术语“连通”、“相连”、“连接”应做广义理解，例如，可以是固定连接，也可以是可拆卸连接，或一体地连接；可以是直接相连，也可以通过中间媒介间接相连。对于本领域的普通技术人员而言，可视具体情况理解上述术语在本申请中的具体含义。Orientation words appearing in the following description are all directions shown in the drawings, and do not limit the specific structure of the present application. In the description of this application, it should also be noted that, unless otherwise expressly specified and limited, the terms "connected", "connected" and "connected" should be understood in a broad sense, for example, it may be a fixed connection or a connectable connection. Detachable connection, or integral connection; it can be directly connected or indirectly connected through an intermediate medium. For those of ordinary skill in the art, the specific meanings of the above terms in the present application can be understood according to specific circumstances.
参见图1和图2，在重水堆中生产Mo-99同位素的辐照靶件，包括：燃料元件1，其包括包壳11、含铀芯子14和端塞16，包壳11端部具有填充开口；端塞16盖设于包壳11端部的填充开口，并与包壳11密封连接，含铀芯子14填充于端塞16与包壳11形成的密封腔室内；端板2，其设置于燃料元件1两端，与若干燃料元件1固定连接；其中，燃料元件1中至少有一根的含铀芯子14设有浓铀燃料，浓铀燃料的 235U富集度在6.0wt％～20.0wt％。优选地，浓铀燃料的 235U富集度在15.0wt％～20.0wt％。 1 and 2, an irradiation target for the production of Mo-99 isotope in a heavy water reactor includes: a fuel element 1, which includes a cladding 11, a uranium-containing core 14 and an end plug 16, the end of the cladding 11 has Filling opening; the end plug 16 is covered on the filling opening at the end of the cladding 11, and is sealed with the cladding 11, and the uranium-containing core 14 is filled in the sealed chamber formed by the end plug 16 and the cladding 11; the end plate 2, It is arranged at both ends of the fuel element 1 and is fixedly connected with several fuel elements 1; wherein, at least one uranium-containing core 14 in the fuel element 1 is provided with enriched uranium fuel, and the enrichment degree of 235 U of the enriched uranium fuel is 6.0wt. %～20.0wt%. Preferably, the enrichment degree of 235 U of the enriched uranium fuel is between 15.0 wt % and 20.0 wt %.
进一步地，浓铀燃料为UO 2、UN、UC、U 3Si 2、U金属、U-Zr合金或U-Al合金或它们与工业纯锆、锆合金、工业纯铝、铝合金、工业纯钼、钼合金、工业纯铌、铌合金、不锈钢、镍合金、碳化硅的任意组合。 Further, the enriched uranium fuel is UO 2 , UN, UC, U 3 Si 2 , U metal, U-Zr alloy or U-Al alloy or their combination with industrially pure zirconium, zirconium alloy, industrially pure aluminum, aluminum alloy, industrially pure Any combination of molybdenum, molybdenum alloy, industrial pure niobium, niobium alloy, stainless steel, nickel alloy, silicon carbide.
进一步地，燃料元件1中除浓铀燃料外的其余材料均采用热中子宏观吸收截面小于10靶恩的材料。Further, the remaining materials in the fuel element 1 except for the enriched uranium fuel are all materials with a macroscopic absorption cross section of thermal neutrons less than 10 barnes.
进一步地，热中子宏观吸收截面小于10靶恩的材料包括如下核级材料：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍或贫铀。Further, the material with a macroscopic thermal neutron absorption cross section of less than 10 barnes includes the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, alumina, beryllium oxide or depleted uranium.
以下具体说明燃料元件的不同实施方式。Different embodiments of the fuel element are described in detail below.
实施例1Example 1
参见图4，本例中的含铀芯子14包含采用实心的浓铀棒或浓铀芯块或浓铀粉体的浓铀芯子15，浓铀芯子15中浓铀燃料的 235U富集度为15～20wt％；包壳11的外径为10.0～14.0mm，其内径为0.5～7.0mm；包壳11、端塞16分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅。 Referring to FIG. 4 , the uranium-containing core 14 in this example includes an enriched uranium core 15 using solid enriched uranium rods or enriched uranium pellets or enriched uranium powder, and 235 U enriched uranium fuel in the enriched uranium core 15 The concentration is 15-20wt%; the outer diameter of the cladding shell 11 is 10.0-14.0mm, and the inner diameter thereof is 0.5-7.0mm; , niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide.
进一步地，含铀芯子14包含采用 235U富集度为19.5wt％的若干UO 2的浓铀芯块沿包壳11的轴向依次叠置而成的浓铀芯子15，包壳11采用壁厚为5.55mm的Zr-4厚壁管。浓铀芯块的直径为2mm，其紧密嵌设在包壳11内。 Further, the uranium-containing core 14 includes the enriched uranium core 15 formed by using a plurality of enriched uranium pellets with a 235 U enrichment of 19.5wt% UO 2 stacked in sequence along the axial direction of the cladding 11. The cladding 11 A Zr-4 thick-walled tube with a wall thickness of 5.55mm was used. The enriched uranium pellets have a diameter of 2 mm and are tightly embedded in the cladding 11 .
UO 2的浓铀芯块在中子辐照下可以生产Mo-99，同时提供适宜的发热量。辐照靶件的最外一圈18根燃料元件1采用图4所示的燃料元件1，内部三圈19根燃料元件1采用图2中所示的常规的燃料元件，单个辐照靶件生产的Mo-99同位素在1000居里，即6天刻度以上(即衰变6天以上还剩的Mo-99的量)。将含有浓铀材料的燃料元件1放置于靶件外 圈，是由于浓铀材料在后续步骤中需要用来提取Mo-99，布置在辐照靶件棒束的外圈方便拆卸；另外，布置在外圈受到自屏蔽效应小，更容易发生核反应。 The enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation. The outermost circle of 18 fuel elements 1 of the irradiation target adopts the fuel elements 1 shown in FIG. 4 , and the inner three circles of 19 fuel elements 1 adopt the conventional fuel elements shown in FIG. 2 , and a single irradiation target is produced The Mo-99 isotope is at 1000 Curies, that is, above the 6-day mark (ie, the amount of Mo-99 left after decaying for more than 6 days). The fuel element 1 containing the enriched uranium material is placed on the outer ring of the target, because the enriched uranium material needs to be used to extract Mo-99 in the subsequent steps, and it is arranged on the outer ring of the irradiation target beam to facilitate disassembly; In the outer ring, the self-shielding effect is small, and the nuclear reaction is more likely to occur.
当然本例中的浓铀芯块也可以采用浓铀粉体替换，也即将浓铀粉体放入包壳11内压实。也可以直接用一整根UO 2的浓铀棒来替换若干个浓铀芯块。 Of course, the enriched uranium pellets in this example can also be replaced with enriched uranium powder, that is, the enriched uranium powder is put into the cladding 11 for compaction. It is also possible to directly replace several enriched uranium pellets with a whole UO 2 enriched uranium rod.
实施例2Example 2
参见图5，本例中的含铀芯子14包括沿中心轴线开通孔的中间厚壁管12、嵌设在中间厚壁管12通孔内作为浓铀芯子15的实心浓铀棒或若干浓铀芯块或浓铀粉体；浓铀芯子15中浓铀燃料的 235U富集度为15～20wt％；中间厚壁管采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；包壳11及端塞16的材料分别采用Zr-4；包壳11外径为10.0～14.0mm，壁厚为0.3～1.0mm；中间厚壁管12外径为9.0～13.0mm，壁厚为1.0～6.25mm；浓铀棒或芯块或粉体直径在0.5～7.0mm之间。 Referring to FIG. 5, the uranium-containing core 14 in this example includes a middle thick-walled tube 12 with a hole along the central axis, a solid enriched uranium rod or a plurality of solid enriched uranium rods embedded in the through hole of the middle thick-walled tube 12 as the enriched uranium core 15. The enriched uranium pellet or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core 15 is 15-20 wt%; the intermediate thick-walled tube adopts any one of the following nuclear grade materials: zirconium alloy, Niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide; the materials of the cladding 11 and the end plug 16 are Zr-4 respectively; the outer diameter of the cladding 11 is 10.0-14.0mm, and the wall thickness is 0.3-1.0 mm; the outer diameter of the middle thick-walled tube 12 is 9.0-13.0 mm, and the wall thickness is 1.0-6.25 mm; the diameter of the enriched uranium rod or pellet or powder is between 0.5-7.0 mm.
进一步地，含铀芯子14包含采用将 235U富集度为15.0wt％、直径为2.7mm的若干UO 2的浓铀芯块作为浓铀芯子15，装入中心轴线开通孔的Zr-4材质的中间厚壁管12内，再将中间厚壁管12装入厚度为0.4mm的薄壁Zr-4材质的包壳11内。其中，中间厚壁管12内的外径为12.2mm、内径为4.75mm。 Further, the uranium-containing core 14 includes a number of enriched uranium pellets with 235 U enrichment of 15.0 wt% and a diameter of 2.7 mm as the enriched uranium core 15 , which are loaded into Zr- 4 material into the middle thick-walled tube 12, and then put the middle thick-walled tube 12 into the cladding 11 of the thin-walled Zr-4 material with a thickness of 0.4 mm. The outer diameter of the middle thick-walled tube 12 is 12.2 mm, and the inner diameter is 4.75 mm.
UO 2的浓铀芯块在中子辐照下可以生产Mo-99，同时提供适宜的发热量。辐照靶件的最外一圈18根元件采用图5中所示的燃料元件1，内部三圈19根燃料元件1采用图2中所示的常规的燃料元件，单个辐照靶件生产的Mo-99同位素在1000居里以上。 The enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation. The 18 elements in the outermost circle of the irradiation target are the fuel elements 1 shown in FIG. 5 , and the 19 fuel elements 1 in the inner three circles are the conventional fuel elements shown in FIG. 2 . A single irradiation target is produced. The Mo-99 isotope is above 1000 Curies.
本例中的浓铀芯块也可以采用浓铀粉体替换，也即将浓铀粉体放入包壳11内压实。也可以直接用一整根UO 2的浓铀棒来替换若干个浓铀芯块。 The enriched uranium pellets in this example can also be replaced with enriched uranium powder, that is, the enriched uranium powder is put into the cladding 11 for compaction. It is also possible to directly replace several enriched uranium pellets with a whole UO 2 enriched uranium rod.
实施例3Example 3
参见图6，本例中浓铀芯子15为在圆筒状的支撑管的外壁涂覆浓铀涂层而成；支撑管13、包壳11分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；包壳11外径为10.0～14.0mm、内径为9.0～13.0mm，支撑管外径为9.0～13.0mm、内径为7.0～12.0mm，浓铀涂层厚度为50～500μm。该浓铀涂层的厚度考虑了不同 235U富集度的浓铀涂层、涂层制造的可行性，如果 235U富集度高，保持 235U总量不变，那么浓铀涂层的量就少一些，反之就多一些；另外，涂层太薄或太厚，都不利于制造。 Referring to FIG. 6 , in this example, the enriched uranium core 15 is formed by coating the outer wall of a cylindrical support tube with enriched uranium coating; the support tube 13 and the cladding 11 are respectively made of any one of the following nuclear-grade materials : zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide; the outer diameter of the cladding 11 is 10.0-14.0mm, the inner diameter is 9.0-13.0mm, the outer diameter of the support tube is 9.0-13.0mm, The inner diameter is 7.0 to 12.0 mm, and the thickness of the enriched uranium coating is 50 to 500 μm. The thickness of the enriched uranium coating takes into account the feasibility of enriched uranium coatings and coatings with different 235 U enrichment degrees. If the enrichment degree of 235 U is high and the total amount of 235 U remains unchanged, then the The amount is less, and vice versa; in addition, the coating is too thin or too thick, which is not conducive to manufacturing.
进一步地，浓铀芯子15为将 235U富集度为10.0wt％的UO 2涂覆在外径为11.8mm、内径为9.8mm的支撑管13外表面形成厚度为160μm的浓铀涂层而成，本例中支撑管13采用不锈钢管。之后再在浓铀芯子15外面加一个Zr-4材质、内径为12.3mm的包壳11形成“夹心”结构。 Further, the enriched uranium core 15 is formed by coating the outer surface of the support tube 13 with an outer diameter of 11.8 mm and an inner diameter of 9.8 mm with UO 2 with a 235 U enrichment of 10.0 wt% to form an enriched uranium coating with a thickness of 160 μm. In this example, the support tube 13 is made of stainless steel. Afterwards, a cladding 11 made of Zr-4 material with an inner diameter of 12.3 mm is added to the outside of the enriched uranium core 15 to form a "sandwich" structure.
UO 2的浓铀涂层在中子辐照下可以生产Mo-99，同时提供适宜的发热量。辐照靶件的最外一圈18根燃料元件采用图6中所示的燃料元件1，内部三圈19根燃料元件1采用图2中所示的常规的燃料元件，单个辐照靶件生产的Mo-99同位素在1000居里以上。 The enriched uranium coating of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation. The 18 fuel elements in the outermost circle of the irradiation target are the fuel elements 1 shown in FIG. 6 , and the 19 fuel elements 1 in the inner three circles are the conventional fuel elements shown in FIG. 2 , and a single irradiation target is produced. The Mo-99 isotope is above 1000 Curies.
实施例4Example 4
参见图7，本例中包壳11内的含铀芯子14通过浓铀芯子15和氧化铍材质的填充芯块17间隔交错放置而成；浓铀芯子15采用浓铀芯块，浓铀芯块中浓铀燃料的 235U富集度为6～20wt％；填充芯块17、端塞16分 别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍；浓铀芯块堆积长度与填充芯块17堆积长度的比值为1:50～1:10 Referring to FIG. 7 , in this example, the uranium-containing cores 14 in the cladding 11 are formed by interlacing the enriched uranium cores 15 and the filling pellets 17 made of beryllium oxide; the enriched uranium core 15 is made of enriched uranium pellets. The enrichment degree of 235 U of the enriched uranium fuel in the uranium pellet is 6-20wt%; the filling pellet 17 and the end plug 16 are respectively made of any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel , aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide; the ratio of the stacking length of enriched uranium pellets to the stacking length of filled pellets 17 is 1:50 to 1:10
进一步地，含铀芯子14采用将 235U富集度为6.0wt％的UO 2的浓铀芯子15和氧化铍材质的填充芯块17间隔交错放置而成。 Further, the uranium-containing core 14 is formed by interlacing the enriched uranium core 15 with UO 2 with a 235 U enrichment of 6.0 wt % and the filled pellets 17 made of beryllium oxide at intervals.
浓铀芯子15为UO 2的浓铀芯块，氧化铍材质的填充芯块17的直径均为12.2mm，UO 2的浓铀芯块和氧化铍的填充芯块17的堆积长度的比值为1:10。 The enriched uranium cores 15 are UO 2 enriched uranium pellets, the beryllium oxide filled pellets 17 are all 12.2 mm in diameter, and the ratio of the stacking lengths of the UO 2 enriched uranium pellets to the beryllium oxide filled pellets 17 is 1:10.
UO 2的浓铀芯块在中子辐照下可以生产Mo-99，同时提供适宜的发热量。辐照靶件的最外一圈18根燃料元件采用图7和图8中所示的燃料元件，内部三圈19根燃料元件1采用图2中所示的常规的燃料元件，单个辐照靶件生产的Mo-99同位素在1000居里以上。 The enriched uranium pellets of UO 2 can produce Mo-99 under neutron irradiation while providing suitable heat generation. The 18 fuel elements in the outermost circle of the irradiation target use the fuel elements shown in Figures 7 and 8, and the 19 fuel elements in the inner three circles use the conventional fuel elements shown in Figure 2. A single irradiation target Pieces of Mo-99 isotope produced in more than 1000 curies.
本发明的设计原理的核心是：考虑对浓缩铀进行中子照射，发生裂变反应后，从靶件中通过放化手段分离Mo-99是效率最高的生产手段。因此，本发明的技术方案是将至少一根燃料元件1中部分天然 235U丰度的UO 2含铀芯子14替换成浓缩铀材料，使本申请辐照靶件中 235U的量与现有常规燃料棒束中的 235U的量大体相同，实现了燃料束替代品的核特性和热工性能基本不变，从而保证了核电厂的安全、经济的发电。由于提高了 235U的富集度，去除了其中大量的 238U，铀材料的量就少了，由此产生的空间通过其他材料支撑或填充以实现 235U裂变材料的定位和传热等功能。针对浓铀燃料、填充材料的选择和浓缩铀与填充材料在棒束中的布置都设计了可行的方案。 The core of the design principle of the present invention is: considering the neutron irradiation of enriched uranium, after the fission reaction occurs, separation of Mo-99 from the target by radiochemical means is the most efficient production means. Therefore, the technical solution of the present invention is to replace part of the UO 2 uranium-containing core 14 with natural 235 U abundance in at least one fuel element 1 with enriched uranium material, so that the amount of 235 U in the irradiation target of the present application is the same as the current one. The amount of 235 U in conventional fuel bundles is roughly the same, so that the nuclear properties and thermal performance of the fuel bundle substitutes are basically unchanged, thereby ensuring the safe and economical power generation of nuclear power plants. Since the enrichment of 235 U is improved, a large amount of 238 U is removed, and the amount of uranium material is reduced, and the resulting space is supported or filled by other materials to realize the functions of positioning and heat transfer of 235 U fissile material. . Feasible schemes are designed for the selection of enriched uranium fuel, filler material and the arrangement of enriched uranium and filler material in the rod bundle.
虽然已经参考优选实施例对本申请进行了描述，但在不脱离本申请的范围的情况下，可以对其进行各种改进并且可以用等效物替换其中的部 件。尤其是，只要不存在结构冲突，各个实施例中所提到的各项技术特征均可以任意方式组合起来。本申请并不局限于文中公开的特定实施例，而是包括落入权利要求的范围内的所有技术方案。Although the application has been described with reference to the preferred embodiments, various modifications may be made and equivalents may be substituted for parts thereof without departing from the scope of the application. In particular, as long as there is no structural conflict, each technical feature mentioned in each embodiment can be combined in any manner. The present application is not limited to the specific embodiments disclosed herein, but includes all technical solutions falling within the scope of the claims.

Claims (8)

  1. 一种在重水堆中生产Mo-99同位素的辐照靶件，其特征在于，包括：An irradiation target for producing Mo-99 isotope in a heavy water reactor, characterized in that it comprises:
    若干根燃料元件，其包括包壳、含铀芯子和端塞，所述包壳端部具有填充开口；所述端塞盖设于所述包壳端部的所述填充开口，并与所述包壳密封连接，所述含铀芯子填充于所述端塞与所述包壳形成的密封腔室内；Several fuel elements include a cladding, a uranium-containing core and an end plug, the end of the cladding has a filling opening; the end plug is covered with the filling opening at the end of the cladding, and is connected with the filling opening. the cladding is sealed and connected, and the uranium-containing core is filled in the sealed chamber formed by the end plug and the cladding;
    端板，其设置于所述燃料元件两端，与若干所述燃料元件固定连接；an end plate, which is arranged at both ends of the fuel element and is fixedly connected with a plurality of the fuel elements;
    其中，所述燃料元件中至少有一根的所述含铀芯子包含浓铀芯子，所述浓铀芯子包含浓铀燃料，所述浓铀燃料的 235U富集度在6.0wt％～20.0wt％。 Wherein, the uranium-containing core of at least one of the fuel elements includes enriched uranium core, the enriched uranium core includes enriched uranium fuel, and the enrichment degree of 235 U of the enriched uranium fuel is 6.0wt%～ 20.0 wt%.
  2. 如权利要求1所述的在重水堆中生产Mo-99同位素的辐照靶件，其特征在于，所述浓铀燃料为UO 2、UN、UC、U 3Si 2、U金属、U-Zr合金或U-Al合金或它们与工业纯锆、锆合金、工业纯铝、铝合金、工业纯钼、钼合金、工业纯铌、铌合金、不锈钢、镍合金、碳化硅的任意组合。 The irradiation target for producing Mo-99 isotope in a heavy water reactor according to claim 1, wherein the enriched uranium fuel is UO 2 , UN, UC, U 3 Si 2 , U metal, U-Zr Alloys or U-Al alloys or any combination of them with industrially pure zirconium, zirconium alloys, industrially pure aluminium, aluminium alloys, industrially pure molybdenum, molybdenum alloys, industrially pure niobium, niobium alloys, stainless steel, nickel alloys, silicon carbide.
  3. 如权利要求1所述的在重水堆中生产Mo-99同位素的辐照靶件，其特征在于，所述燃料元件中除所述浓铀燃料外的其余材料均采用热中子宏观吸收截面小于10靶恩的材料。The irradiation target for producing Mo-99 isotope in a heavy water reactor according to claim 1, wherein the rest of the materials in the fuel element except the enriched uranium fuel are made of thermal neutron macroscopic absorption cross section smaller than 10 barn materials.
  4. 如权利要求3所述的在重水堆中生产Mo-99同位素的辐照靶件，其特征在于，所述热中子宏观吸收截面小于10靶恩的材料包括如下核级材料：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍或贫铀。The irradiation target for producing Mo-99 isotope in a heavy water reactor according to claim 3, wherein the material with a macroscopic absorption cross-section of thermal neutrons less than 10 barnes comprises the following nuclear grade materials: zirconium alloy, niobium Alloys, molybdenum alloys, stainless steel, aluminum alloys, nickel-based alloys, silicon carbide, aluminum oxide, beryllium oxide or depleted uranium.
  5. 如权利要求1～4任一项所述的一种在重水堆中生产Mo-99同位素的辐照靶件，其特征在于：The irradiation target for producing Mo-99 isotope in a heavy water reactor according to any one of claims 1 to 4, characterized in that:
    所述浓铀芯子采用实心的浓铀棒或浓铀芯块或浓铀粉体；所述浓铀芯子中浓铀燃料的 235U富集度为15～20wt％； The enriched uranium core adopts a solid enriched uranium rod or enriched uranium pellet or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core is 15-20wt%;
    所述包壳的外径为10.0～14.0mm，其内径为0.5～7.0mm；The outer diameter of the cladding shell is 10.0-14.0mm, and the inner diameter thereof is 0.5-7.0mm;
    所述包壳、端塞分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅。The cladding shell and the end plug respectively adopt any one of the following core-grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, and silicon carbide.
  6. 如权利要求1～4任一项所述的一种在重水堆中生产Mo-99同位素的辐照靶件，其特征在于：The irradiation target for producing Mo-99 isotope in a heavy water reactor according to any one of claims 1 to 4, characterized in that:
    所述含铀芯子包括沿中心轴线开通孔的中间厚壁管、嵌设在所述中间厚壁管的所述通孔内的浓铀芯子，所述浓铀芯子采用实心浓铀棒或若干浓铀芯块或浓铀粉体；所述浓铀芯子中浓铀燃料的 235U富集度为15～20wt％； The uranium-containing core includes an intermediate thick-walled tube with a hole along the central axis, and an enriched uranium core embedded in the through hole of the intermediate thick-walled tube, and the enriched uranium core adopts a solid enriched uranium rod. or several enriched uranium pellets or enriched uranium powder; the enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium core is 15-20wt%;
    所述中间厚壁管采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；The intermediate thick-walled pipe adopts any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide;
    所述包壳及端塞的材料分别采用Zr-4；The materials of the cladding shell and the end plug are respectively Zr-4;
    所述包壳外径为10.0～14.0mm，壁厚为0.3～1.0mm；所述中间厚壁管外径为9.0～13.0mm，壁厚为1.0～6.25mm；所述浓铀棒或浓铀芯块或浓铀粉体直径在0.5～7.0mm之间。The outer diameter of the cladding is 10.0-14.0mm, and the wall thickness is 0.3-1.0mm; the outer diameter of the middle thick-walled tube is 9.0-13.0mm, and the wall thickness is 1.0-6.25mm; the enriched uranium rod or enriched uranium The diameter of pellets or enriched uranium powder is between 0.5 and 7.0 mm.
  7. 如权利要求1～4任一项所述的一种在重水堆中生产Mo-99同位素的辐照靶件，其特征在于：The irradiation target for producing Mo-99 isotope in a heavy water reactor according to any one of claims 1 to 4, characterized in that:
    所述浓铀芯子为在圆筒状的支撑管的外壁涂覆浓铀涂层而成；The enriched uranium core is formed by coating the outer wall of the cylindrical support tube with enriched uranium coating;
    所述支撑管、包壳分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅；The support tube and the cladding are respectively made of any one of the following nuclear-grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide;
    所述包壳外径为10.0～14.0mm、内径为9.0～13.0mm，所述支撑管外径为9.0～13.0mm、内径为7.0～12.0mm，所述浓铀涂层厚度为50～500μm。The outer diameter of the cladding is 10.0-14.0 mm, the inner diameter is 9.0-13.0 mm, the outer diameter of the support tube is 9.0-13.0 mm, the inner diameter is 7.0-12.0 mm, and the thickness of the enriched uranium coating is 50-500 μm.
  8. 如权利要求1～4任一项所述的一种在重水堆中生产Mo-99同位素的辐照靶件，其特征在于：The irradiation target for producing Mo-99 isotope in a heavy water reactor according to any one of claims 1 to 4, characterized in that:
    所述含铀芯子为沿包壳的长度方向依次交错嵌设在其内的采用浓铀燃料的浓铀芯子和填充芯块，所述浓铀芯子采用浓铀芯块；The uranium-containing cores are enriched uranium cores and filling pellets which are sequentially interleaved along the length direction of the cladding and are embedded in it using enriched uranium fuel, and the enriched uranium cores are enriched uranium pellets;
    所述浓铀芯块中浓铀燃料的 235U富集度为6～20wt％； The enrichment degree of 235 U of the enriched uranium fuel in the enriched uranium pellet is 6-20wt%;
    所述填充芯块、端塞分别采用包括如下核级材料中的任一种：锆合金、铌合金、钼合金、不锈钢、铝合金、镍基合金、碳化硅、氧化铝、氧化铍；The filling pellets and the end plugs are respectively made of any one of the following nuclear grade materials: zirconium alloy, niobium alloy, molybdenum alloy, stainless steel, aluminum alloy, nickel-based alloy, silicon carbide, aluminum oxide, beryllium oxide;
    所述浓铀芯块堆积长度与填充芯块堆积长度的比值为1:50～1:10。The ratio of the enriched uranium pellet stacking length to the filling pellet stacking length is 1:50˜1:10.
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