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快热耦合系统的中子学计算工具——采用确定论方法 被引量:1

Deterministic Neutronics Calculation Method for Fast/Thermal-Combined System
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摘要 对于既具有高能量外中子源又包含热中子区域的快热耦合系统,本文将离散坐标法Sn与栅格计算程序相结合,给出可用于快热耦合系统的中子学确定论计算工具。用该方法计算了启明星1号次临界装置的keff,并给出了计算结果。 For a system consisting of both high energy external neutron source and ther mal neutron zone, a neutronics calculation method is developed based on the combination of the Sn and cell parameter calculation codes. The method is used in the calculation of keff, for a sub critical system prior to the later use for a fast/thermal combined system, and the calculated keff is given.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2006年第2期186-188,共3页 Atomic Energy Science and Technology
基金 国家重点基础研究规划项目(G19990226)
关键词 快热耦合系统 中子学计算方法 增殖因子计算 fast/thermal-combined system neutronics calculation method multiplyfactor calculation
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  • 1黄锦华,张国书,阳彦鑫.快热耦合系统的中子学计算工具——采用确定论方法[J].原子能科学技术,2006,40(2):186-188. 被引量:1
  • 2[4]Briesmeister J F.MCNP-A general Monte Carlo N-particle transport code [Z].Radiation transport group,LANL,2000.
  • 3史永谦.启明星1号装置[R].北京:中国原子能科学研究院,2003.
  • 4O'DELL R D. Revised users manual for TWODANT: A code package for two-dimensional accelerated neutral particle transport[R]. New Mexico:Los Alamos National Laboratory, 1984.
  • 5MARKOVSKIJ D V, HUANG J, YOU C H.Some neutronics aspects of the Chinese Tokamak engineering test breeder TETB-Ⅲ : IAE-5628/8[R]. Moscow: Russian Research Center Kurchatov Institute, 1993.
  • 6WIENKE H, HERMAN M. FENDL/MG-2. 0 and FENDL/MC-2. 0, the processed cross-section libraries for neutron-photon transport calculations, version 1 of February 1998, summary documentation report IAEA-NDS-176 Rev 0[R].vienna: International Atomic Energy Agency,1998.
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  • 8BRIESMEISTER JUDITH F. MCNP A general Monte-Carlo N-particle transport code [Z].New Mexico: Los Alamos National Laboratory,2000.

共引文献4

同被引文献6

  • 1史永谦.启明星1号装置[R].北京:中国原子能科学研究院,2003.
  • 2O'DELL R D. Revised users manual for TWODANT: A code package for two-dimensional accelerated neutral particle transport[R]. New Mexico:Los Alamos National Laboratory, 1984.
  • 3MARKOVSKIJ D V, HUANG J, YOU C H.Some neutronics aspects of the Chinese Tokamak engineering test breeder TETB-Ⅲ : IAE-5628/8[R]. Moscow: Russian Research Center Kurchatov Institute, 1993.
  • 4WIENKE H, HERMAN M. FENDL/MG-2. 0 and FENDL/MC-2. 0, the processed cross-section libraries for neutron-photon transport calculations, version 1 of February 1998, summary documentation report IAEA-NDS-176 Rev 0[R].vienna: International Atomic Energy Agency,1998.
  • 5刘萍.基于ENDF-B-VI的WIMS-82群截面库[R].北京:中国核数据中心,2003.
  • 6BRIESMEISTER JUDITH F. MCNP A general Monte-Carlo N-particle transport code [Z].New Mexico: Los Alamos National Laboratory,2000.

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