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CARR自给能探测器实验设计与验证研究

Study on Self-Powered Neutron Detector Experiment Design and Verification in CARR
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摘要 辐照靶件的释热计算对堆内实验设计影响重大。本文依据在CARR堆上开展的自给能探测器实验,分析了不同核评价数据库在辐射俘获反应释热计算上的差异来源,并对较早版本数据库的计算结果进行了一定的修正。实验结果表明,以ENDF/B-VⅢ.0等库为代表的数据库计算结果更为合理,并建议研究者在进行后续堆内实验设计时,关注KERMA因子的能量平衡情况,优先采用数据更为完备的核评价数据库进行计算。 Heat releasing calculation for irradiated targets have a tremendous influence on in-core experiment design.Based on the self-powered neutron detector experiment in CARR,the difference of heat releasing calculation results on radioactive capture reaction with several evaluated nuclear data libraries has been studied,and a modification to the calculation with earlier database edition has been implemented.The experimental results show that the heat releasing calculation results with ENDF/B-VⅢ.0 are more reasonable,and a evaluated nuclear data library edition with more data is always suggested to be used for future in-core experiment design.Users should check if the KERMA factors and energy balance are adequate or not to get reliable results.
作者 乔雅馨 陶杰 吴小飞 QIAO Yaxin;TAO Jie;WU Xiaofei(China Institute of Atomic Energy,Beijing 102413,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2023年第3期517-521,共5页 Nuclear Science and Engineering
基金 国家重点研发计划资助项目(2002YFB1902600)。
关键词 自给能探测器 释热计算 核评价数据库 CARR Self-powered neutron detector Heat releasing calculation Evaluated nuclear data library CARR
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  • 1孙德仁 沈峰 刘燕 等.971工程放射性同位素辐照靶件模拟实验报告[R].北京:中国原子能科学研究院,2001..
  • 2仲言.重水研究堆[M].北京:原子能出版社,1988.572-575.
  • 3中国核动力设计研究院.反应堆堆芯相关组件内热源计算报告[R].2005.
  • 4J F Briesmeister, et al. MCNP-A General Monte Carlo N-Particle Transport Code[R]. Version 4C. Los Alamos National Laboratory, Report LA-13709-M, 2000.
  • 5The Members of the Cross Section Evaluation Working Group. Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VIIFR']. New York~ National Nuclear Data Center Brookhaven National Laboratory, 2006.
  • 6张竞上.中子引发轻核反应的统计理论[M].北京:科学出版社,2009.
  • 7MacFARLANE R E, MUIR D W. NJOY99, code system for producing pointwise and multi- group neutron and photon cross sections from ENDF/B data[R]. USA: Los Alamos National Laboratory, 2000.
  • 8TRELLUE H R, LITTLE R C, LEE M B. New ACE-formatted neutron and proton libraries based on ENDF/B-VII. 0[R]. USA.. LANL, 2008.
  • 9GE Z G, ZHUANG Y X, LIU T J, et al. The updated version of Chinese evaluated nuclear data library (CENDL-3. 1)[J]. Journal of Korean Physical Society, 2011, 59(2) : 1 052-1 056.
  • 10CHADWICK M B, OBLOZINSKY P, HER- MAN M, et al. ENDF/B-VII. 0: Next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 2006, 107(12): 2 931-3 118.

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