清洁解控和退役若干动向与新发展

对国际辐射防护协会第10届大会(IRPA-10)涉及的清洁解控和退役问题作了论述,包括排除、豁免、清洁解控和废物最少化;退役工程技术的发展,包括去污技术、切割解体技术、探测技术;介绍了一个研究堆退役例子和加速器退役;最后,还论及了退役中受关注的一些问题,如：石墨废物、混凝土废物、重水堆退役的氚防护、退役时间和退役废物量等。     

清洁解控和退径若干动向与新发展

对国际辐射防护协会第１０届大会（ＩＲＰＡ－１０）涉及的清洁解控和退没问题作了论述。包括排除、豁免、清洁解控和废物最少化;退没工程技术的发展,包括去污技术、切割解体技术、探测技术;介绍了一个研究堆退役例子和加速器很役;最后,还论及了退役中受关注的一些问题,如：石墨废物、混凝土废物、重水堆退役的氚防护、退役时间和退役废物量等。     

重水研究堆退役废物再利用研究

实现废物再利用是废物最小化的重要措施之一,从废物流中将有潜在利用价值的物料分离出来实现再利用可大幅减少对环境的影响。本文以中国原子能科学研究院重水研究堆退役为实例研究了放射性废物再利用问题。通过全面分析和计算重水研究堆在退役期间产生的各类废物,得出具有一定数量的物料有潜在的利用价值,可直接或经适当处理后再利用在其他行业领域中。研究表明,通过采取废物最小化控制措施（如废物分类和废物流分离等）,采用适当的去污技术和执行清洁解控要求,至少可使重水研究堆退役过程中产生的几十吨钢铁、10 t铝材和5 t重水实现再利用。     

浅谈回旋加速器退役拆解过程中实现放射性废物最小化的方法

本文主要针对陕西某三甲医院回旋加速器实施退役过程中,放射性废物最小化处理方法的分析和总结,旨在为今后类似回旋加速器退役治理过程中放射性废物处理提供良好的实践经验。本文中的回旋加速器主要用于生产医用放射性同位素,因设备老旧无法满足生产要求,故对其实施退役,以达到场所和设备清洁解控的目的。本次退役范围主要包括回旋加速器主体及主机房、药物合成室及其配套用房,需要进行清洁治理的为回旋加速器主体及主机房。在对回旋加速器进行拆解和大块部件切割之前和切割过程中,进行现场监测和实验室采样分析,通过现场监测结果和产生的放射性废物源项分析,按照废物最小化原则,对低放射性废物和极低放射性废物进行分类收集整备并送贮,对达到清洁解控水平的部件进行清洁解控与资源回收利用。本次退役共产生放射性废物约25吨,依据本文论述方法分拣出的可解控废物约12吨,实现了废物最小化。     

放射性物料的清洁解控

放射性物料的清洁解控是放射性废物最小化的一项重要手段。为了进一步指导物料解控,本文介绍了与清洁解控水平相关的三个国家标准,明确了解控标准的适用条件,说明了使用标准进行物料解控过程中应该注意的问题,并结合解控审管实践对解控过程中几个重要的审管要求进行了讨论,最后提出了申请解控文件应包括的主要内容。     

亚洲核合作论坛2006年度"放射性废物管理研讨会"

1 概要 亚洲核合作论坛(FNCA) 2006年度"放射性废物管理研讨会"于2006年11月20日至24日在北京召开.本次会议由日本文部科学省(MEXT)与中国国家原子能机构共同主办,由中国核工业集团公司和日本原子力产业协会(JAIF) 联合承办.共有来自FNCA成员国澳大利亚、中国、印度尼西亚、日本、韩国、马来西亚、菲律宾、泰国和越南的30 多名代表参加了会议.会议主要讨论了FNCA各成员国的放射性废物管理进展,包括法规、管理体制、低中放废物处置设施概念设计、放射性废物的处理与整备和退役中的清洁解控等.     

放射性废物清洁解控水平的研究进展及个人体会

放射性废物清洁解控水平的研究进展及个人体会任宪文（中国辐射防护研究院，太原，０３０００６）１前言近年来，ＩＡＥＡ对清洁解控水平进行了大量研究。但由于这项工作的复杂性，至今只给出了某些情景下的豁免水平（清洁解控水平），距彻底解决此问题还有相当差距。清洁...     

适用豁免和清洁解控水平的监测——IAEA第67号技术报告简介

介绍了IAEA技术报告《适用豁免和清洁解控水平的监测》废物豁免和解控监测的技术,以帮助核设施运营单位在国家审管部门的监管下开展有计划的解控检测活动。     

放射性废物管理和核设施退役中几个问题的讨论

从满足放射性废物管理和核设施退役工作的需要出发,讨论了《电离辐射防护与辐射源安全基本标准》中有关排除、豁免、解控以及排放、废源处置、去污、废物最少化、防护最优化等几项规定的实施问题,并对其中一些问题提出了继续深入研究的意见。     

核电厂放射性废物源头控制管理技术研究

核电厂放射性废物源头控制管理技术是实现放射性废物最小化的关键措施。通过对核电厂放射性废物源头控制管理技术的分析,从废物产生量的控制、清洁解控管理和再循环再利用角度介绍了废物源头控制措施及方法,对国内近几年废物源头控制管理技术良好实践进行讨论,提出了国内核电厂运行废物源头控制管理和放射性废物管理的思考和建议。     

放射性废物安全的主题分类和部分成果评介

将放射性废物安全初步分类为废物处理与整备设施安全,废物贮存设施安全,废物与废放射源处置设施安全,流出物排放安全,污染物料回收利用安全,退役与环境整治安全,排除、豁免、解控,废物优化管理和废物最少化,废物管理政策法规标准和规划,废物安全监管和安全文化素养等10个主题.按照上述主题分类,对我国放射性废物安全领域近年来的研发进展做了述评.     

Non-technical Considerations in Regulation of Very Low Level Radioactive Waste: Comparative Analysis of Japan and the United States

With presently over 400 commercial nuclear power reactors being operated worldwide, many of which will retire within the next 50 years, the future generation of world nuclear energy depends upon strategies for low level waste management and decommissioning of those reactors. These strategies must address issues such as: economical feasibility, environmental and health standards, post-decommissioning land and facility usage. This paper considers those issues in the context of the inherently intertwined social and technical characteristics, with an emphasis on the management of very low level wastes. Until now 70 commercial power reactors have been decommissioned, however, most have been relatively small in comparison to those that will be preparing for decommissioning in the next 50 years. The resulting materials will add to the already increasing amounts of waste and material from nuclear reactors. Since the move to harmonization of clearance level regulation may have critical impacts on the environment and health as well as decommissioning costs and priority setting this paper examines both the areas of consensus and uncertainties between countries regarding very low level waste regulations for recycling of materials arising from decommissioning, against the background of international discussions. In conclusion, we discuss the need for deliberation regarding the assumptions and cultural factors.     

Identification and evaluation of facilitation techniques for decommissioning light water power reactors

This paper describes a study sponsored by the US Nuclear Regulatory Commission to identify practical techniques to facilitate the decommissioning of nuclear power generating facilities. The objectives of these “facilitation techniques” are to reduce public/occupational exposure and/or reduce volumes of radioactive waste generated during the decommissioning process.The paper presents the possible facilitation techniques identified during the study and discusses the corresponding facilitation of the decommissioning process. Techniques are categorized by their applicability of being implemented during the three stages of power reactor life: design/construction, operation, or decommissioning. Detailed cost-benefit analyses were performed for each technique to determine the anticipated exposure and/or radioactive waste reduction; the estimated cost for implementing each technique was then calculated. Finally, these techniques were ranked by their effectiveness to facilitate the decommissioning process.This study is a portion of the NRC's evaluation of decommissioning policy and supports the modification of regulations pertaining to the decommissioning process. The findings can be used by the utilities in the planning and establishment of the activities to ensure all objectives of decommissioning will be achieved.     

铀同位素浓缩设施的退役处理

1985年9月至1986年12月完成了一套铀同位素浓缩试验设施的退役。本次退役属第三类退役形式,要求设施全部拆除迁离,厂房改作其它用途。退役活动包括:设施拆除、部件拆卸解体、包装、运输、去污、辐射监测、废物管理及物资处理。依靠以化学方法为主,辅以机械的和熔炼方法的去污手段,使1300吨金属部件表面污染水平降至允许限值以下。退役废物总量约50吨。监测结果表明,退役活动未造成对人员、环境明显影响。     

某城市放射性废物库退役的辐射影响评价

为了使城市放射性废物库退役后可无限制开放,本研究探讨废物库退役辐射影响评价的关键问题,评价人员和周围环境的辐射影响。对比源项调查和控制限值,判定污染区域;按退役实施方案得到放射性废物的产生量和整备前的活度水平;利用经验公式估算职业人员的外照射、内照射剂量,分析公众的辐射影响。选取退役要执行的放射性指标和适宜场地的控制限值,提出退役施工中实现废物最小化的具体措施。经估算得到退役实施的最大个人剂量为3.9 mSv,低于剂量约束值5 mSv。剂量实测值比评价结果低约2个数量级,退役活动中工作人员受到的辐射剂量满足国家标准的要求,退役辐射环境影响在可接受范围。     

Final Status of the Decommissioning of Research Reactors in Korea

A decommissioning project for the Korean Research Reactors KRR-1 and KRR-2 was started in 1997 and had been carried out with the goal of completion by the end of 2008. All the facilities were dismantled and the building surfaces decontaminated. The radioactive waste was packed into 200 liter drums and 4m³ containers and temporarily stored on site until their final disposal at the national repository facility. Some of the releasable waste was freely released and utilized for non-nuclear industries. The assessment of the residual radioactivity was carried out according to the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM), and accordingly, the safety of the site release was verified. The site and buildings will be cleared for reuse for non-nuclear purposes after a review of the assessment. In this paper, the final status of the decommissioning of research reactors in Korea including dismantlement processes, waste management, and a final assessment for unrestricted use of the site and buildings as the final goal of the decommissioning project will be described.     

核设施退役信息数据库的结构与功能设计

核设施退役工程是一项不仅需要考虑拆除（毁）设备、建筑物,还要考虑辐射影响和核废物处理的复杂工程,其拆除（毁）工作具有高危险、高污染的特点,因此建立针对核设施退役项目的信息系统辅助退役工程很有意义。本文通过收集退役活动数据(设备物资数据、源项数据、辐射剂量数据等)设计退役信息数据库,开发了基于退役数据库的信息管理系统,该系统可对数据库中各类信息数据（照片、图纸、辐射数据、时间等）进行录入、删除、修改、查询等基本操作,并根据各类数据处理流程的特点分功能模块进行相应数据信息的管理,并对不同数据信息进行分析。该系统可提升退役过程中的管理能力,优化工程安排,减少作业人员所受辐射剂量,是顺利进行退役活动的必要基础。     

核设施退役中几种"问题"废物的管理

核设施退役产生的废物不同于运行或日常维护过程中产生的废物,由于其中某些废物的特殊性质被认为是有“问题”的废物,需进行特殊的管理。本文介绍了几种含有危险性材料或有毒物质类的“问题”废物的管理。     

Treatment and geological disposal of waste from NET pre-design

Within the European Fusion Technology programs Studsvik RadWaste AB has performed studies on fusion waste treatment and disposal for several years. This paper deals with the treatment and geological disposal of radioactive waste from NET operation and decommissioning. Results from calculations on radioactive waste fluxes for the operation and decommissioning of NET are reported. The calculations are based on the NET predesign report published 1993 and include results for the exchangeable in-vessel and external parts of the machine as well as permanent reactor components. Different aspects of treatment, packaging, transportation, and interim storage of the waste are discussed. The volumes of waste conditioned for final disposal are preliminarily quantified, according to German and Swedish scenarios for radioactive waste disposal. A total repository volume of approximately 45,000 m³ is required in the German Scenario and 35,000 m³ is required in the Swedish Scenario. Results from dose rate calculations for NET waste in final repositories are presented for the Swedish Scenario. This work was financially supported by the Swedish Natural Science Research Council (NFR) and the European Atomic Energy Community, under an association contract between Euratom and Sweden.