期刊文献+

VVER机组燃料破损导致放射性碘危害的评估与防护探讨 被引量:3

Discussion of radioactive iodine hazard estimation and protection caused by fuel defect for VVER unit
在线阅读 下载PDF
导出
摘要 压水堆核电厂运行过程中可能发生燃料棒破损。燃料棒一旦破损,所包容的高水平放射性碘等裂变气体将释放至一回路,并可能进一步释放到厂房导致较高的空气污染,增加工作人员受到内照射的风险。对VVER机组燃料棒破损可能导致的碘危害进行了估算和分析,结果表明:即使1根燃料棒破损也可导致大修期间堆厂房放射性碘空气污染水平高达84DAC(derived air concentration)。结合电厂实践从一回路净化除碘、控制碘向厂房空气释放和扩散、空气净化和个人防护等方面探讨了放射性碘危害的控制和防护措施,并提出了后续应对类似情况的建议。 There is probability of fuel rods damage in PWR during operation. If the fuel rods damaged,the fission gases such as radioiodine will be released to the air of building,increasing the risk of internal exposure to personnel. According to the estimation of iodine hazard due to fuel rods damage for VVER unit,one damaged fuel rod can lead to air contamination of radioiodine as high as 84 DAC. With reference to the practical NPP,radioiodine hazard control and protection measures such as the primary circuit purification,control of iodine releasing and diffusing to the air,air purification and personal protection are discussed,and some suggestions for similar situations are proposed.
出处 《辐射防护》 CAS CSCD 北大核心 2015年第3期176-179,187,共5页 Radiation Protection
关键词 燃料棒 破损 碘危害 评估 防护 fuel rod damage radioiodine hazard estimation protection
  • 相关文献

参考文献1

二级参考文献7

  • 1环境保护部,国家质量监督检验检疫总局.GB6249--2011核动力厂环境辐射防护规定[S].北京:中国环境科学出版社,2011:2-6.
  • 2US NRC. Title 10 Code of Federal Regulations Contents of applications; technical information [ Z]. Washington DC, U.S. Nuclear Regulatory Commission, 2011:434.
  • 3US NRC. Regulatory Guide 1. 183 Alternative radiological source terms for evaluating designbasis accidents at Nuclear Washington DC, U. S. Commission, 2000:20.
  • 4Power Reactors [ Z ]. Nuclear Regulatory US NRC. NUREG - 0800 Standard review plan for the review of safety analysis reports for Nuclear Power Plants[Z]. Washington DC, U.S. Nuclear Regulatory Commission, 2007 : 15.6.3 - 3.
  • 5US NRC. Results of initial screening of generic issue 197 iodine spiking phenomena [ R ]. Washington DC, U. S. Nuclear RegulatoryCommission, 2006.
  • 6Lewis B J, Iglesias FC, Postma AK, et al. Iodine spiking model for pressurized water reactors [ J ]. Journal of Nuclear Materials, 1997, 244:153 - 167.
  • 7Adams JP, Atwood CL. Probability of the iodine spike release rate during an SGTR [ R ]. Idaho Falls, U. S. A: Idaho National Engineering Laboratory, 1989.

共引文献3

同被引文献25

引证文献3

二级引证文献4

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