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极低水平放射性废物处置:立陶宛在方法和长期安全方面的案例。

Disposal of very low-level radioactive waste: Lithuanian case on the approach and long-term safety aspects.

机构信息

Lithuanian Energy Institute, Nuclear Engineering Laboratory, 3 Breslaujos, Kaunas LT44403, Lithuania.

Brunel University London, Institute of Energy Futures, College of Engineering, Design and Physical Sciences, UB8 3PH Uxbridge, United Kingdom.

出版信息

Sci Total Environ. 2019 Jun 1;667:464-474. doi: 10.1016/j.scitotenv.2019.02.373. Epub 2019 Feb 27.

Abstract

Decommissioning of nuclear power plants typically requires management of hundreds of thousands of cubic meters of waste with very low levels of radioactivity. Such very low-level waste (VLLW) is suitable for disposal in simple landfill type facilities. The only nuclear power plant in the Republic of Lithuania, the Ignalina NPP, was finally shut down at the end of 2009. Final management of the existing operational radioactive waste and that arising during the decommissioning will require the disposal of 60,000 m of very low-level short-lived solid waste. An overview of the implementation of the landfill disposal facility for very low-level radioactive waste at the Ignalina NPP site and the main aspects of long-term safety assessments based on national regulations as well as the IAEA's recommendations including the siting process are presented in this paper as well as a short description of the disposal concept and the characteristics of the waste intended for disposal in the landfill. Water pathway scenarios as well as intrusion scenarios have been investigated following an IAEA methodology. It has been defined that C is the greatest contributor to the total dose in the case of water pathway scenarios. In the case of intrusion scenarios, the main contribution to the total dose is from radionuclides Nb and Cs. In all the considered cases, the total value of the annual effective exposure dose remains quite well (orders of magnitude) below the value of the dose constraint established by regulations of Lithuania. Uncertainty analysis is carried out to define the influence of various factors on the obtained results of the safety assessment.

摘要

退役核电厂通常需要管理数十万立方米放射性很低的废物。这种极低水平的废物(VLLW)适合在简单的垃圾填埋类型设施中处置。立陶宛共和国唯一的核电厂,伊格纳利纳核电站,终于在 2009 年底关闭。现有运行放射性废物和退役期间产生的放射性废物的最终管理需要处置 60000 立方米的极低水平短寿命固体废物。本文概述了伊格纳利纳核电站场址极低水平放射性废物填埋处置设施的实施情况,以及基于国家法规和国际原子能机构建议的长期安全评估的主要方面,包括选址过程,还简要介绍了处置概念和拟在填埋场处置的废物的特性。按照国际原子能机构的方法,研究了水途径情景和入侵情景。已经确定,在水途径情景中,C 是总剂量的最大贡献者。在入侵情景中,总剂量的主要贡献来自 Nb 和 Cs 放射性核素。在所有考虑的情况下,年有效暴露剂量的总价值仍然相当低(数量级)低于立陶宛法规规定的剂量约束值。进行不确定性分析以确定各种因素对安全评估结果的影响。

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