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聚变驱动次临界堆双冷嬗变包层多群中子截面数据库共振自屏效应计算与分析 被引量:2

Resonance self-shielding effect analysis of neu tron data libraries applied for the dual-cooled waste transmutation blanket o f the fusion-driven subcritical system
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摘要 依据聚变驱动次临界反应堆 (FDS I)系统设计方案 ,使用Njoy和Transx程序 ,制作了 2 5群、1 75群、62 0群忽略和考虑共振自屏效应的中子截面核数据库 ,用Anisn程序计算了系统的有效增殖系数和各种反应率。结果表明 ,共振自屏效应对FDS I系统的各种反应率有很大的影响。 Based on the Fusion-Driven Subcritical Sy st em(FDS-I) , the 25 groups,175 groups and 620 groups neutron nuclear data librar ies with/withoutresonance self-shielding correction are made withthe Njoyand Transx codes, and the K eff and reactionr atesare calculated with the Anisncode. The conclusion indicates that the resonance self-shielding effect affects the reactionrates stro ngly.
出处 《核科学与工程》 CAS CSCD 北大核心 2004年第3期282-288,共7页 Nuclear Science and Engineering
基金 国家自然科学基金资助项目 (10 175 0 6 8) 中科院知识创新工程项目资助
关键词 聚变驱动 次临界堆 双冷嬗变包层 次临界反应堆 反应率 核数据库 中子 效应 截面数据 FDS resonance self-shielding effect reactive cross secti on reactive ratio Bondarenko method
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参考文献13

  • 1Arzu Alpan F, et al. Effect of Energy Self-Shielding Methods on 238U for Criticality Safety Problems, PHYSOR 2004-The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago. Illinois, April 25~29, 2004.
  • 2Hanshaw Heath L, et al. Estimation of the Effects of Self-Shielding on Multigroup Reactor Vessel Fluence Calculations[J]. Trans.Am.Nucl.Soc.,1994, 71:386-388.
  • 3Chikara Konno , et al. Comment to unresolved resonance data in JENDL-3.3 , Japan Atomic Energy Research Institure,Symposium on Nuclear Data,2003.
  • 4Chikara KONNO, et al. Some Remarks on Multigroup Library, Japan Atomic Energy Research Institute,Symposium on Nuclear Data,1997.
  • 5Bondarenko I I. Group constants for Nuclear Reactor Calculations Consultants Bureau, New York.1964.
  • 6MacFarlane R E, et al. The NJOY Nuclear Data Processing System Version 91, LA-12740-M Manual. UC-413, 1994, 10.
  • 7MacFarlane R E. TRANSX 2: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes, 1993, 12.
  • 8Engle W W, et al. Anisn, One-dimensional discrete ordinates transport code system with anisotropic scattering, K1693 (March, 1967).
  • 9刘成安,张毓泉,吕荀,刘朝芬,田东风,巫德章,刘忠兴.中子群常数共振自屏效应的研究[J].高技术通讯,1991,1(9):25-30. 被引量:1
  • 10王庆明,黄锦华.多群中子输运计算中的共振自屏问題[J].核科学与工程,1991,11(1):73-79. 被引量:1

二级参考文献26

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同被引文献17

  • 1汪卫华,吴宜灿,王红艳,柯严,黄群英.聚变驱动次临界堆双冷嬗变包层热工水力学参数设计与分析[J].核科学与工程,2004,24(1):93-96. 被引量:21
  • 2Mollendorff U V,et al. A14-MeV Neutron Transmiion Experiment on Vanadium. Presented at the 19th Symposium on Fusion Technology[C]. 1996.
  • 3Wu Y,et al. Integral Data Tests of the FENDL-1,EFF-2,EFF-3 and JENDL-FF Fusion Nuclear Data Libraries[R]. Forschungsentrum arlsruhe Research Report FA-5953. IN 0947-8620. 1998.
  • 4Yican Wu,et al. Integral Data Test of FENDL-2 Fusion Nuclear Data Library with Neutroncs Shiled Experiments[J]. Journal of Nuclear Science and Technology,2000,supplement 1.
  • 5Devin B V,et al. Neutron Leaage Spectra from Spherical Iron Shells. Forschungsentrum arlsruhe,Techniund Umwelt,Interner Bericht 31.06.30/01A.
  • 6Chun-jing Gao,et al. Integral Data Test of HENDL1.0/MG and VisualBUS with Neutronics Shielding Experiments(I)[J]. Plasma Science and Technology,2004,6(5):2 507~2 513.
  • 7Chun-jing Gao,et al. Integral Data Test of HENDL1.0/MG with Neutronics Shielding ExperimentsII)[J]. Plasma Science and Technology,2004,6(6).
  • 8DOORS 3.2,One-,Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System,RSICC Computer Code Collection,CCC-650,1998.
  • 9Perry R T,et al. A Combined P3 VITAMIN-C,MACLIB-IV,Coupled 25 Neutron-21 Gamma Group Cro Section Library – The UW Cro Section Library. UWFDM-390. University of Wisconsin,1980.
  • 10MacFarlane R E,et al. The NJOY Nuclear Data Proceing System,Version 91[J]. LA-12740-M. Los Alamos National Laboratory ,1994.

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