期刊文献+

基于AST方法的核电厂LOCA释放源项计算分析 被引量:1

Analysis of Release Source Term in LOCA for NPP Based on AST Method
下载PDF
导出
摘要 根据AST方法建立了AP1000LOCA放射性核素活度计算模型,研究事故后安全壳及环境中放射性核素活度的变化。结果表明:事故后安全壳气空间内各核素的放射性活度呈先增大后减小的趋势,40min时达到最大。根据核素性质,将其分为不考虑母核衰变的核素和考虑母核衰变的核素。事故发生40min后,前者在安全壳内的活度指数减小,典型核素有131~135I、83 Krm等,后者由于母核衰变的影响导致其在安全壳内的活度减小趋势放缓,典型核素有85 Kr、133 Xem、133 Xe和135 Xe等。I和Cs由于受自然去除机制的去除作用,事故几小时后其向环境的累积释放量增长非常缓慢;对于Kr和Xe,半衰期较长的核素向环境的累积释放量不断增大,半衰期较短的核素在事故几小时后向环境的累积释放量趋于平衡。 The radioactivity calculation model in loss of coolant accident(LOCA)for AP1000 was established based on AST method and the change of radioactivity in containment and environment was studied after LOCA.The results show that the nuclide radioactivity in containment atmosphere first increases and then decreases with time,and reaches maximum at 40 min.According to the natural characteristics,the radionuclides can be divided into nuclides without nucleus decay and nuclides with nucleus decay.After 40 min of the accident,the activity of the former in containment exponentially decreases,such as ^131-135 I and ^83 Kr^m,while the activity of the latter decreases slowly due to nucleus decay,such as ^85 Kr,^133 Xe^m,^133 Xe and 135 Xe.After several hours of LOCA,the cumulative release amount of I and Cs to environment increases slowly because of natural removal mechanism.For Kr and Xe,the cumulative release amount of the longer half-life nuclides to environment increases with time,while that of the shorter half-life nuclides reaches balance after a few hours of LOCA.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第7期1268-1272,共5页 Atomic Energy Science and Technology
基金 国家科技重大专项资助项目(2013ZX06002001)
关键词 LOCA AST 安全壳 环境 释放源项 LOCA AST containment environment release source term
  • 相关文献

参考文献4

二级参考文献23

  • 1杨洪润,李兰,沈瑾.秦山核电二期工程事故源项分析[J].核动力工程,2003,24(z1):69-72. 被引量:5
  • 2陈晓秋,岳会国,林权益.双层安全壳压水堆LOCA事故的放射性后果分析审查[J].辐射防护通讯,2005,25(4):1-8. 被引量:8
  • 3DINUNNO J J, ANDERSON F D, BAKER R E, et al. Calculation of distance factors for power and test reactor sites, TID-14844 [R]. Washington, USA: U.S. Atomic Energy Commision, 1962.
  • 4NRC. Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors, RG 1. 183 [R]. Washington,USA: U. S. Nuclear Regulatory Commission, 2000.
  • 5Palisades Plant. Amendment to renewed facility operating license: Alternative radiological source term, NRC/ADAMS ML072470667[R]. Washington, USA: U.S. Nuclear Regulatory Commission, 2007.
  • 6Calvert Cliffs NPP, Unit 1&2. Amendment to renewed facility operating license: Alternative radiological source term, NRC/ADAMS ML072210207[R]. Washington, USA: U. S. Nuclear Regulatory Commission, 2007.
  • 7NRC. Assumption used for evaluating the potential consequences of a loss of coolant accident for pressurized water reactors, RG 1.4[R]. Washington, USA: U.S. Nuclear Regulatory Commission, 1974.
  • 8CROFF A G. A user's manual for the ORIGEN2 computer code, ORNL/TM-7175[R]. Oak Ridge, USA: Oak Ridge National Laboratory, 1980.
  • 9NRC. Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-water Nuclear Power Reactors. Regulatory Guide 1. 195, 2003.
  • 10中华人民共和国国家标准 GB18871--2002.电离辐射防护与辐射源安全基本标准.[S].,..

共引文献15

同被引文献8

引证文献1

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