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基于热堆的钍铀转换过程中^(232)U生成的模拟计算 被引量:5

Simulative calculation of ^(232)U productions in thorium-uranium transform process based on thermal reactor
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摘要 在钍铀燃料循环过程中生成的232U的衰变子体具有强放射性,对燃料循环具有重要影响。本工作采用ORIGEN2、SCALE5程序,以及基于Bateman方法编写的程序,分析了在不同条件下,热堆中钍反应生成232U的规律。一般情况下,232U主要由232Th的(n,2n)反应链生成,而在中子能谱更软情况下,230Th对232U生成贡献增大;CANDU型重水堆和压水堆的含钍燃料组件的燃耗计算结果表明,铀中232U含量随燃耗深度增加而变大,同时初始230Th/Thtotal大小直接线性影响卸料燃耗时232U/Utotal或232U/233U。 The decay products of 232U produced in the thorium-uranium fuel cycle emit high energy γ-rays.This affects the fuel cycle greatly.In this paper,the 232U productions in thermal reactor using thorium fuel are analyzed by ORIGEN2,SCALE5 and the code based on the Bateman method.Under normal situation,232U is mainly produced by 232Th(n,2n) reaction chain,and more quantity of 230Th can be transformed into 232U while the neutron spectrum is softer.The burnup calculation of CANDU reactor and PWR assembly indicates that the232U in uranium increase with the burnup,and230Th in fresh thorium has linear correlation with232U/Utotalor232U/233U at discharge burnup.
出处 《核技术》 CAS CSCD 北大核心 2012年第5期395-400,共6页 Nuclear Techniques
关键词 钍铀燃料循环 232U 230Th 中子能谱 熔盐堆 Thorium-uranium fuel cycle 232U 230Th Neutron spectra Molten Salt Reactor
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参考文献14

  • 1Thorium fuel cycle - Potential benefits and challenges. IAEA-TECDOC-1450, 2005.
  • 2Jungmin Kang, Frank N. yon Hippel, U-232 and the Proliferation-Resistance of U-233 in Spent Fuel[J]. Science & Global Security, 2001, 9:1-32.
  • 3Takaaki Ohsawa, Masaharu Inoue. Analysis of neutron yields and energy spectra from spent molten-salt reactor fuel[J]. Ann Nucl Energy, 1994, 21(4): 207 -210.
  • 4Belle J, Berman R M. Thorium dioxide: properties and nuclear applications, DOE/NE-0060, 1984.
  • 5Saed Mirzadeh, Phillip Walsh. Numerical evaluation of the production of radionuclides in a nuclear reactor (Part I) [J]. Appl Radiat Isot, 1998, 49(4): 379-382.
  • 6Croft A G. A user's manual for the ORIGEN2 computer code. ORNL/TM-7175, 1980.
  • 7Dehart M D, Bowman S M. Reactor physics methods and analysis capabilities in SCALE[J]. Nuclear Technology, 2011, 174:196-213.
  • 8Croft A G, Bjerke M A, Morrison G W, et al. Revised uranium-plutonium cycle PWR and BWR models for the ORIGEN computer code. ORNL/TM-6051, 1978.
  • 9Zhang J H, Bao B R, Xia Y X, et al. The dependence of build-up 233U, 232U, 233pa and fission products from ThO2 irradiated in HFETR on integral thermal neutron fluxes and neutron spectra[J]. Journal of Radioanalytical and Nuclear Chemistry, Letters, 1987, 117(2): 121-127.
  • 10Horhoiany G, Moscalu D R, Olteanu G, et al. Development of SEU-43 fuel bundle for CANDU type reactors[J]. Ann Nucl Energy, 1998, 25(16): 1363-1372.

二级参考文献7

  • 1Generation IV Roadmap NERAC Subcommittee. Technology Goals for Generation IV Nuolear Eaetlff System[R]. NERAC. May 2001.
  • 2Michel Lung, Otto Gremm. Perspective of the Thrum Fuel Cycle[J]. Nuclear Engineering and Design, 1998,180:133 - 146.
  • 3Altiparmakov D V. WIM S-AECL Theory Manual[M].COG 00-77, AECL. September 2001.
  • 4Douglas S R. WIMS-AECL Release 2-5d Users Manual[M]. COG-94-52(Rcv. 4), AECL. July 2000.
  • 5Chan P S W, Tsang K T, Buss D B. Re.actor Physics of NG CANDU[C]. Reactor Physics of NG CANDU 22nd Canadian Nuclear Society Conference, Toronto, 2001, 7:10 - 13.
  • 6Horhoianu G, Moscall D R, OLTEANU G, et al. Development of SEU-43 Fuel Bundle for CANDU Type Reactors[J]. Ann Nucl Energy, 1998, 25 (16): 1363 - 1372
  • 7朱鑫官,蔡剑平,HankChow.CANDU反应堆物理程序和方法[J].核动力工程,1999,20(6):538-542. 被引量:3

共引文献3

同被引文献19

  • 1顾忠茂.钍资源的核能利用问题探讨[J].核科学与工程,2007,27(2):97-105. 被引量:27
  • 2张家骅,包伯荣.我国钍资源调查及钍-铀燃料循环研究[A].张家骅.钍-铀核燃料循环研究[C].上海:中国科学院上海应用物理研究所,2009:22-26.
  • 3Troyanov M F. Thorium fuel utilization: options and trends[R]. Vienna: IAEA-TECDOC-1319, 2002.
  • 4Furukawa K, Lecocq A, Kato Y, et al. Thorium molten-salt nuclear energy synergetics[J]. Journal of Nuclear Science and Technology, 1990, 27(12): 1157-1178.
  • 5Furukawa K, Mitachi K, Kato Y, et al. Small molten-salt reactors with a rational thorium fuel-cycle[J]. Nuclear Engineering and Design, 1992, 136(1): 157-165.
  • 6Murogov V M, Zinin A J, Ilyunin V G, et al. Fast reactors with different fuels in uranium-plutonium and combined fuel cycle[G]. IPPE-1920, 1998, 23(1): 203-206.
  • 7Rutten H J, Teuchert E. Advanced safety features of pebble bed HTR's with Th-utilization[R]. Julich: KFA, 1993.
  • 8Yu J Y, Wang K, Sollychin R, et al. Thorium fuel cycle of a thorium-based advanced nuclear energy system[J]. Progress in Nuclear Energy, 2004, 45(1): 71-84.
  • 9Chang J J, Chang J P, Won I K. Dynamic analysis of a thorium fuel cycle in CANDU reactors[J]. Annals of Nuclear Energy, 2008, 35(10): 1842-1848.
  • 10Yamamoto T, Suwarno H, Kayano H, et al. Development of new reactor fuel materials[J]. Journal of Nuclear Science and Technology, 1995, 32(3): 260-262.

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