辐射防护 ›› 2025, Vol. 45 ›› Issue (S1): 32-37.

• “核设施退役与核环境安全”专刊 • 上一篇    下一篇

飞凤山低中放固体废物处置场安全全过程系统分析研究进展

陈运利, 相秀娟, 罗国洲   

  1. 中核清原环境技术工程有限责任公司,北京 100037
  • 收稿日期:2025-03-26 发布日期:2026-01-15
  • 作者简介:陈运利(1981—),男,2004年毕业于南华大学核工程与核技术专业,高级工程师。E-mail: chenyunli@cnnc-everclean.com

Progress of safety case study of southwest low and intermediate level radioactive waste disposal repository

CHEN Yunli, XIANG Xiujuan, LUO Guozhou   

  1. CNNC Everclean Environmental Engineering Co., Ltd., Beijing 100037
  • Received:2025-03-26 Published:2026-01-15

摘要: 参照国际原子能机构(IAEA)安全导则SSG-23要求,在2019年至2023年开展了飞凤山处置场安全全过程系统分析研究。研究形成了适合飞凤山处置场的特征、事件和过程(FEPs)清单和评价景象,完成了处置场场址区域未来气候变化预测,构建了处置场处置单元混凝土演变模型和地下水位长期动态模型,并给出了代表性核素在混凝土和原状土中迁移参数。该研究成果一方面作为我国制定安全全过程系统分析导则的一个试点,另一方面为其他近地表处置设施开展安全全过程系统分析研究提供参考。

关键词: 近地表处置, 安全评价, 安全全过程系统分析

Abstract: In accordance with the requirements of IAEA Safety Guide SSG-23, a safety case study for the Southwest radioactive waste disposal facility was conducted from 2019 to 2023. This research has developed a site-specific FEPs (Features, Events, and Processes) list and assessment scenarios for the facility, projected future climate change prediction in the facility site region, established a concrete evolution model for the disposal units and a long-term dynamic model of groundwater level. Migration parameters are also provided for representative radionuclides in both concrete and undisturbed soil. This research achievement could serve as a demenstration for China to develop guidelines for safety process system analysis, and provide reference for other near surface disposal facilities to conduct safety process system analysis research.

Key words: near surface disposal, safety evaluation, safety case study

中图分类号: 

  • TL942