内幕

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY
D. Roudil, L. Aldave de Las Heras
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引用次数: 0

摘要

欧洲原子能机构H2020欧洲项目INSIDER(受限环境下退役中废物最小化的改进核场所表征)于2017年6月启动,为期4年;目前包括来自10个欧洲国家的17个合作伙伴。该项目侧重于应用于废物驱动综合方法的放射性表征,包括采样总体策略和设计。其目标是改善来自退役和拆除核场址或设施和/或其他受限环境的中(MA)和高放射性(HA)水平废物的管理。优化的准则是运行退役效率、安全性和成本。该项目的结果将增加对发展和发展所产生的放射性废物的数量和特征的了解,并增加对今后储存和处置终点的健全定义的信心。因此,INSIDER主要关注退役作业上游的预表征问题。该方法以先进的统计处理和建模为基础,结合现场或实验室验证的测量技术和方法,最终目标是经济收益,提高安全性和可持续性。该项目的技术方法一方面是开发不同的采样策略,结合表征方法,其性能在代表性情况下已知,另一方面,通过代表退役工地典型配置的3个具体案例研究,确定该方法的贡献并验证其在实际情况下的有效性:-核反应堆:Mol (SCK-CEN)的BR3反应堆容器;-在ISPRA(联合研究中心)安装燃料/废物循环:污水池;-事后管理:污染土壤(CEA)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
INSIDER
The H2020 Euratom European project INSIDER (Improved Nuclear Site Characterization for waste minimization in decommissioning under constrained environment) was launched in June 2017 for a duration of 4 years; it currently includes 17 partners from 10 European countries. The project is focused onto radiological characterization applied to waste-driven integrated approaches, including the sampling overall strategy and design. Its objectives are to improve the management of waste with medium (MA) and high radioactivity (HA) levels coming from nuclear sites or facilities under D&D (Decommissioning and dismantling) and/or other constrained environments. The optimization criteria refer to operational decommissioning efficiency, safety and costs. The outcome of the project will increase knowledge on the amounts and characteristics of radioactive waste resulting from D&D and increase confidence on the sound definition of subsequent storage and disposal end points. INSIDER is thus mainly focused on the issues of precharacterization upstream of decommissioning operations. The methodology is based on advanced statistical processing and modelling, coupled with validated measurement techniques and methods, in situ or in laboratory, with a final objective of economic gains, and improved safety and sustainability. The technical approach of the project is on one hand to develop different sampling strategies, coupled with characterization methods whose performances are known in representative situations, and on the other hand to qualify the contribution of this approach toand validate its effectiveness in real situations on 3 concrete case studies representing typical configurations of decommissioning worksites: – Nuclear reactor: BR3 reactor vessel at Mol (SCK-CEN); – Installation of the fuel/waste cycle: effluent tanks at ISPRA (JRC); – Post-incident management: contaminated soils (CEA).
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
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