UC1取样计划,废液储罐,JRC Ispra

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY
G. V. Oertzen, O. Nitzsche, Artur Hashymov
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引用次数: 1

摘要

INSIDER工作包3 (WP 3)的目标是根据统计方法,起草一份在受限环境中初始核场地表征的抽样指南。在本文中,为WP 3提出了可交付成果3.4 (D 3.4),其中可交付成果3.1 (D 3.1)至3.3 (D 3.3)中制定的策略应用于代表现有退役场景的三个参考用例中的第一个。目前的讨论集中在用例1 (UC1): Ispra(意大利)JRC站点的液体废物存储设施。在D 3.2中提出的表征策略以一步一步的方法应用于分析预先存在的信息(通过使用预抽样问卷获得),并利用可用的输入来制定足以允许放射学表征的抽样计划。拟议的取样计划遵循三步方法,即通过无损检测确定活性浓度可能升高的程度,对已识别的层进行有偏取样,最后在混合储罐内容物后进行无偏取样。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
UC1 sampling plan, liquid waste storage tanks, JRC Ispra
The objective of INSIDER work package 3 (WP 3) is to draft a sampling guide for initial nuclear site characterization in constrained environments, based on a statistical approach. In this paper, deliverable 3.4 (D 3.4) is presented for WP 3, where the strategy developed in deliverables 3.1 (D 3.1) to 3.3 (D 3.3) is applied to the first of three reference use cases representative of existing decommissioning scenarios. The present discussion focuses on use case 1 (UC1): the liquid waste storage facility at the JRC site of Ispra (Italy). The proposed characterization strategy developed in D 3.2 is applied in a step by step approach to analyse the pre-existing information (obtained through the use of a pre-sampling questionnaire), and to utilise the available inputs towards the development of a sampling plan sufficient for allowing radiological characterization. The proposed sampling plan follows a three-step approach, i.e. determination of possible elevation in activity concentration by non-destructive testing, biased sampling of layers identified, and finally unbiased sampling after mixing of tank contents.
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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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