期刊文献+

西安脉冲堆定量安全目标初步研究

Preliminary study on quantitative safety goals of the Xi'an pulsed reactor
下载PDF
导出
摘要 为了提高西安脉冲堆运行安全管理水平,结合西安脉冲堆纵深防御特点及现有运行安全水平,以概率安全分析结果为依据,分析提出了西安脉冲堆安全目标体系构成和安全目标定量化数值。研究表明,西安脉冲堆安全目标体系应补充概率安全目标和辐射防护定量约束目标,概率安全目标包含堆芯损伤频率值、少量放射性释放频率值。提出的定量化安全目标建议为:堆芯损伤频率限值1×10^(-5)/堆年,少量放射性释放频率限值1×10-^(7)/堆年;正常工况下,公众有效剂量不超过0.1 m Sv·a^(-1),工作人员有效剂量不超过2 m Sv·a^(-1);事故工况下的定量辐射防护目标还需要进一步的研究。 To promote the safety standards and operation management in Xi'an pulsed reactor,the construction of a system of safety goals and its quantitative value were put forward and analyzed on the basis of the result of probabilistic safety assessment( PSA),with considering of the characteristic of XAPR's defense in-depth and its operational safety level. The results demonstrated that XAPR safety goals should be supplemented with objectives of probability quantitative and radiation protection dose constraints. Safety goals were proposed including core damage frequency of less than 1 × 10^-5 per reactor year,and small release frequency of less than 1 × 10^-7 per reactor year; public dose of less than 0.1 m Sv·a^-1,and occupational dose of less than 2 m Sv·a^-1 in normal conditions. In accident conditious however,further work about the protection goals is expected.
出处 《辐射防护》 CAS CSCD 北大核心 2017年第5期380-386,共7页 Radiation Protection
关键词 西安脉冲堆 安全目标 定量目标 研究堆 Xi'an pulsed reactor safety objective measurable safety goal research reactor
  • 相关文献

参考文献12

二级参考文献88

  • 1曲静原,薛大知.核安全目标制定与评估中的若干问题[J].辐射防护通讯,2005,25(6):10-14. 被引量:5
  • 2西北核技术研究所.西安脉冲堆最终安全分析报告.内部资料,2007.
  • 3General Atomic Company. Safety analysis report for the atomic energy research institute seoul KOREA: GA-9867. USA: GA, 1970.
  • 4Croft A G. ORIGEN2-A revised and updated version of the oak ridge isotope generation and depletion code. ORNL-5621, USA: ORNL Oak Ridge, 1980.
  • 5IAEA. Accident analysis for nuclear power plants.Safety Reports Series No. 23, Vienna: IAEA, 2002.
  • 6国家核事故应急办公室.为验证遵守辐射防护规定的剂量限值,计算气态和液态放射性物质排放时引起的照射剂量采用的模型、假定和参数.孙呈志译.1995.
  • 7ICRP. Age-dependent doses to members of the public from intake of radio nuclides. Part 4 : Inhalation dose coefficients. ICRP Publication 71. Annals of the ICRP Vol. 25 No. 3-4, 1995.
  • 8中华人民共和国国家标准.核电厂环境辐射防护规定.GB6249—86.北京:中国标准出版社,1987.
  • 9国家核安全局.研究堆厂址选择.核安全法规技术文件.HAF·J0005.1992.
  • 10IAEA. Generic assessment procedures for determining protective actions during a reactor accident. IAEA-TECDOC-955. Vienna: IAEA, 1997.

共引文献47

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部