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燃料组件程序ROBIN-1.7的验证和确认 被引量:3

Verification and Validation of Lattice Code ROBIN-1.7
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摘要 利用国际公开基准题开展ROBIN-1.7燃料组件计算程序的共振计算、输运计算、燃耗计算等模块的验证工作。分别利用临界基准问题、蒙特卡罗程序、OECD NEA燃耗基准问题及其他输运-燃耗基准问题等对ROBIN-1.7程序进行确认。验证及确认结果表明,ROBIN-1.7程序的共振计算、输运计算、燃耗计算等模块及集成计算结果是正确的;ROBIN-1.7程序对各问题主要物理参数(如反应性、棒功率分布以及同位素浓度)的计算精度达到了国际同类商业程序的水平,满足在压水堆中工程应用的要求。 Verification and validation of lattice code ROBIN-1.7 is performed by using international public benchmark problems, which include critical experiments data, depletion benchmark problems of OECD NEA and other neutron transport-depletion calculations with MCNP code. The result(reactivity, pin power distribution, isotope concentration) shows that independent modules of ROBIN-1.7 such as resonance treatment module, neutron transport module and depletion module are developed and integrated correctly. It is also demonstrated that ROBIN-1.7 has reached the industry level for PWR application.
出处 《核动力工程》 EI CAS CSCD 北大核心 2014年第S2期98-101,共4页 Nuclear Power Engineering
关键词 ROBIN-1.7 组件程序 程序验证 程序确认 ROBIN-1.7,Lattice code,Code verification,Code validation
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参考文献8

  • 1Lewis E.Benchmark specification for deterministic 2-D/3-D MOX fuel assembly transport calculations without spatial homogenisation (C5G7MOX)[].OECD/NEA Report.2001
  • 2Yamamoto,Akio.Evaluation of background cross section for heterogeneous and complicated geometry by the enhanced neutron current method[].Journal of Nuclear Science and Technology.2008
  • 3Mosteller, Russell D.,Eisenhart, Laurence D.,Little, Robert C.,Eich, Walter J.,Chao, Jason.Benchmark calculations for the Doppler coefficient of reactivity[].Nuclear Science Journal.1991
  • 4Akio YAMAMOTO,Tadashi IKEHARA,Takuya ITO,Etsuro SAJI.Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels[].Journal of Nuclear Science and Technology.2002
  • 5David C Carpenter,Joseph H. Wolf III.The log linear rate constant power depletion method[].PHYSOR.2010
  • 6IAEA.WIMS-D library update:final report of a coordinated research project[]..2007
  • 7ANL.Neutronic Depletion benchmark problems.argonne code center:benchmark problem book. ANL-7416 . 1977
  • 8Straw L E,Barry R F.Criticality calculations for uniform water-moderated lattices[].Nuclear Science Journal.1965

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