期刊文献+

北山预选场区未来人类活动辐射环境评估

Radiation Environmental Assessment of Future Human Activities in Beishan Pre-selected Sites
下载PDF
导出
摘要 通过分析计算高放废物地质处置库关闭后,人类未来活动深井取水情景下,附近居民的受照剂量,得出在处置库系统保持稳定及屏蔽作用有效时,居民在围岩外深井取水,接受到的处置库泄漏核素所致剂量的最大值之和为0.522μSv/a,辐射环境影响可接受。 After analyzing the exposure dose of the nearby residents under the deep well water in-take scenario in the high-level radioactive waste geological repository.It is concluded that when the repository system is stable and the shielding effect is effective,the residents take water from the deep well outside the surrounding rock,and the sum of the maximum doses of the received nuclides from the disposal warehouse is 0.522μSv/a,and the radiation environmental impact is acceptable.
作者 陈海龙 廉冰 赵杨军 李洋 杨洁 CHEN Hai-long;LIAN Bing;ZHAO Yang-jun;LI Yang;YANG Jie(China Institute for radiation protection,Taiyuan 030006,China)
出处 《核电子学与探测技术》 CAS 北大核心 2020年第4期616-620,共5页 Nuclear Electronics & Detection Technology
基金 国防科学技术基金(20131221)资助。
关键词 高放废物 地质处置系统 安全评价 High-level Radioactive W aste(HL W) Geological Disposal System Safety Assessment
  • 相关文献

参考文献2

二级参考文献46

  • 1OECD/NEA. Lessons learnt from ten performance assessment studies[R]. Paris, France: OECD/NEA, 1991.
  • 2OECD/NEA. Review of safety assessment methods, disposal of radioactive waste, a report of the performance assessment advisory group of the radioactive waste management committee[R]. Paris,France: OECD/NEA, 1991.
  • 3OECD/NEA. Confidence in the long-term safety of deep geological repositories, its development and communication[R]. Paris, France OECD/NEA, 1999.
  • 4IAEA. Safety indicators in different time frames for the safety assessment of underground radioactive waste repositories[R].Vienna, Austria: 1AEA-TECDOC-767, IAEA, 1994.
  • 5JNC. Project to establish the scientific and technical basis for HLW disposal in Japan[R]. JNC1410 2000-01, 2000.
  • 6IAEA. IAEA Safety Glossary: Terminology used in nuclear safety and radiation protection [R ]. Vienna: IAEA, 2007.
  • 7IAEA. Safety assessment methodologies for near surface disposal facilities, Volume 1: Review and enhancement of safety assessment approaches and tools[R]. Vienna: IAEA, 2004.
  • 8Sumerling T J, Grogan H A, Smith P A. Scenario development for Kristallin-I[R]. Wettingen: NAGRA, 1993.
  • 9NEA. Disposal of radioactive waste: Review of safety assessment methods [R]. Paris : OECD/NEA, 1991.
  • 10Ross B. Scenarios for repository safety analysis [J]. Engineer Geology, 1989, 26: 285-299.

共引文献6

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