Scenarios and Pathways of Radionuclide Releases from Near-Surface Waste Disposal Facilities: A Brief Overview of Historical Evidence

Q2 Energy

Nuclear and Radiation Safety Pub Date : 2020-09-15 DOI:10.32918/nrs.2020.3(87).03

D. Bugai, R. Avila

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引用次数: 1

Abstract

The very low-level waste (VLLW) produced during decommissioning of nuclear facilities can be suitable for disposal in landfill type facilities. Considering the similarities in design, the experience gained in near-surface disposal of radioactive waste in trenches and vaults is relevant to the issue of VLLW disposal in landfills. This paper presents a brief review of internationally reported cases of radionuclide releases from near-surface disposal facilities. Based on this review, the conclusions are made that the following radionuclide release and exposure scenarios should be accounted for in safety assessment of VLLW disposal in landfills: i) leaching from waste to groundwater by atmospheric precipitations; ii) bath-tubing scenario; iii) scenarios caused by extreme meteorological and hydrological events (erosion, flooding, etc.); iv) human intrusion. The gaseous transport deserves attention for a number of relevant radionuclides, such as (C-14, Rn-222, etc.). In addition, the possibility of early degradation of engineered containment structures (soil covers, bottom seals) should be cautiously considered.

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近地表废物处理设施释放放射性核素的情景和途径:历史证据的简要概述

核设施退役过程中产生的极低放射性废物(VLLW)适合在填埋型设施中进行处理。考虑到设计上的相似之处，在沟槽和拱顶中近地表处理放射性废物的经验与在垃圾填埋场中处理vlll废物的问题有关。本文简要回顾了国际上报道的近地表处置设施释放放射性核素的案例。在此基础上，得出以下结论:在垃圾填埋场处置放射性废物的安全性评估中，应考虑以下放射性核素释放和暴露情景:1)通过大气降水从废物中浸出到地下水中;Ii)浴管情景;Iii)极端气象和水文事件(侵蚀、洪水等)造成的情景;Iv)人为入侵。一些相关的放射性核素，如(C-14、Rn-222等)的气态输运值得注意。此外，应谨慎考虑工程密封结构(土壤覆盖物、底部密封)早期退化的可能性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear and Radiation Safety Energy-Nuclear Energy and Engineering

CiteScore

0.80

自引率

0.00%

发文量

期刊介绍： General issues of nuclear energy use; nuclear energy (reactor theory and calculations, operation of nuclear power plants, NPP safety analysis (probabilistic safety analysis, deterministic safety analysis), research reactors, nuclear fuel and structural materials, fuel elements; neutron physics; general safety issues; decommissioning of nuclear facilities; long-term operation, spent fuel and radioactive waste management; radiation safety; I&C, physical protection.