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压水堆辐照监督管中子注量计算方法改进研究 被引量:3

Study on the Improvement of Calculation Method for the Neutron Fluence in the Irradiation Monitoring Tube of the Reactor Vessel
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摘要 总结分析了目前压水堆辐照监督管中子注量的工程计算方法和流程。通过理论研究和敏感性分析,提出了部分改进的计算方法。根据实际核电厂辐照监督管快中子注量计算结果与实测值的比较,证明了本文提出的改进方法的合理性和先进性。 The present engineering calculation method and flow on the neutron fluence in the irradiation monitoring tube of the reactor vessel are summarized and analyzed.This paper presents some improved calculation methods on the basis of theoretical studies and sensitivity analyses.Calculation results of the actual monitoring tube of the reactor vessel based on this method are shown.It proves that the calculation method is more reasonable and advanced by comparison between the calculated values and measured data.
作者 石秀安 苏耿华 包鹏飞 SHI Xiu-an;SU Geng-hua;BAO Peng-fei(China Nuclear Power Technology Research Institute,Shenzhen of Guangdong Prov.518026,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2018年第4期585-589,共5页 Nuclear Science and Engineering
关键词 辐照监督管 中子注量 计算方法 改进 Surveillance capsule Neutron fluence Calculation method Improvement
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  • 1CAREW J F, HU K, ARONSON A, et al. PWR and BWR pressure vessel fluence calculation benchmark problems and solutions[R]. Washington: U. S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research, 2001.
  • 2杨玉中.基于蒙特卡罗输运技术的压力容器及辐照监督管中子注量计算方法研究及应用[C]//第十届全国核反应堆数值计算和粒子输运学术会议暨2004年度反应堆物理会议文集.秦山,2004:535-543.
  • 3RHOADES W A, CHILDS R L. TORT-DORT two- and three-dimensional discrete ordinates transport version 2.8.14[R]. USA: Oak Ridge National Laboratory, 1994.
  • 4BRIESMEISTER J F. MCNP4C Monte Carlo Nparticle transport code[R]. USA: Los Alamos National Laboratory, 2000.
  • 5U.S. Nuclear Regulatory Commission. NUREG/CR-6115, BNL-NUREG-52395, PWR and BWR pressure vessel fluence calculation benchmark problems and solutions [R]. USA: Brookhaven National Laboratory, 2001.
  • 6WILLIAMS J G, VEHAR D W, RUDDY F H, et al. Impact of the ENDF/B-VI cross sections on the RPV fluence determination[R]. West Conshohoken: American Society for Testing and Materials, 2000.
  • 7AFCEN.DesignandConstructionRulesforMechanicalComponents of PWR Nuclear Islands[].RCC-M.2002
  • 8.
  • 9Standard Practice for Design of Surveillance Programs for Light-water Moderated Nuclear Power Reactor Vessels. ASTME185-82 . 1982
  • 10U.S.NRC.Radiation Embrittlement of Reactor Vessel materials[].NRC RG.1998

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