"乏燃料管理安全和放射性废物管理安全联合公约"述评

“乏燃料管理安全和放射性废物管理安全联合公约”是迄今为止有关放射性废物管理方面最重要的全球性公约,亦是继1994年“核安全公约”以来核安全国际法领域又一新的突破。本文简要介绍“乏燃料管理安全和放射性废物管理安全联合公约”的主要内容,并讨论了其存在的问题及对策。     

法国的放射性废物量

【德国《原子经济》1992年第7期第332页报道】法国法学家Jena-Yves Le Deaut就法国至2000年产生的放射性废物作出估计。对于放射性小于10Bq/g的废物,未见到官方的报道。Le Deaut估计这类废物约有65万米~3,并必须加以回用。放射性在10至100 Bq/g的“A”级废物约为10万米~3,应存放在特殊的埋藏场里。“A”类放射性废物的     

长寿命放射性废物管理战略比较

【英国《国际核工程》2005年2月刊报道】长寿命放射性废物备选管理战略比较(Compas)是欧洲委员会第五个框架计划中的一个项目,实施时间为2001年11月1日至2003年10月30日。针对欧盟成员国和申请加入欧盟的国家所面临的乏燃料和长寿命放射性废物(即后处理产生的高放废物和长寿命中低放废物)管理问题,该项目对中、西欧国家相应的政策和战略进行比较研究。比较结果反映了这些国家在2003年9月1日之前的废物管理战略状况。Compas项目主要研究下述四个方面:待管理的废物以及改变废物属性的方法;对已制定的战略产生重大影响的问题;已制定的或正在考…     

美国一元化乏燃料管理系统和有效的低放废物处置系统

【英国《国际核工程》 1998年 5月刊报道】　处理核电废物需要有独特的政策和技术。核燃料循环自始至终都有废物收集、包装、管理和安全处置的问题。其他许多有益于社会的活动 ,也产生“低放”废物。这些活动包括生物医学和药物研究、生产、疾病诊断和治疗。核电站产生低放废物与其他来源相比是很少的 ;通过技术改进 ,废物的平均体积在近 2 0年里已经减少到原来的十分之一。1980年低放废物政策法载有关于低放废物处置的国家政策。在国家政策的指导下 ,各州单独或与其他州订立合同发展处置设施。自从该法通过以来 ,已经订立了 9个合同 ,但是…     

低水平放射性废物和混合废物的商用处理技术（六）

4.1 0固化 /稳定化本节中描述的技术是将化学或放射性有害物固化成一种固体废物体 ,限制废物可浸出的表面积 ,限制废物的溶解性或消除废物中的有毒组分。所有这些工艺过程都使用无机或有机添加剂 ,其作用是作为化学粘接剂、废物体或工艺性能的增强剂、或防止放射性扩散。一种固化技术的应用和选择通常应考虑到 EPA有害废物处理标准、废物管理问题、或者处置场的废物接收标准。以下讨论的是几个典型的固化 /稳定化工艺技术及其对特殊种类废物的适用性。4.1 0 .1波特兰水泥固化系统采用波特兰水泥作为固化 /稳定剂来固化废物。在这类系统中 …     

我国放射性废物管理模式涉及的主要方面

本文介绍了在实践中逐步形成和完善的我国放射性废物管理模式所涉及的主要方面,包括：废物管理体系的确立和核设施内部废物管理机构的设计,以安全为目的,处置为核心的从“出生到坟墓”的全过程管理,放心物最小量化,废物审计,废物跟踪制度,对废物从产生到处置的全过程实行许可证制度。     

在辐射防护和安全中一些概念的转变

本文讨论了在辐射防护和安全中一些概念的转变，其中主要是：用“实践”和“干预”的观点代替单一的“实践”的观点；用辐射防护体系代替单一的剂量限值；用一般职业保健服务的观点代替以发现辐射效应和放射性禁忌症为目的的医学监护的观点；用以处置为中心，包括废物的产生、处理、前处置和处置在内的全面的放射性废物管理代替以临时贮存为终点仅包括收集和贮存的废物管理。并注意正确理解“约束”的概念，加强核设施的防护，加强天然辐射源产生的照射的研究。     

三门核电站放射性固体废物跟踪管理系统

放射性废物管理是核电站重要的管理活动之一。从废物的产生到处理、整备和暂存,三门核电站对放射性固体废物实施全过程跟踪管理。为此,三门核电站开发的放废管理系统不仅可按照废物种类、统计周期、电站机组等进行废物统计、跟踪,还可按废物具体来源(如具体工作或工艺系统)进行统计、跟踪,最终为放射性固体废物管理及有针对性地制定废物最小化措施提供基础信息。     

核燃料循环与核废物

核废物,又称放射性废物,是指放射性活度大于国家主管机关所规定的“免管量(Exempt Quantity)”,且今后不再被利用的含放射性核素或污染有放射性核素的任何物质。因此核废物可产生于任何应用放射性核素的单位,但其数量和放射性水平不尽相同。     

放射性废物管理(Ⅰ)

一、引言放射性废物的管理包括放射性废物技术上的治理管理或行政上的管理,本文所涉及的主要是前者。 1.放射性废物管理的重要性在核工业和核技术应用中,在为人类产生效益的同时还产生放射性废物。这些废物不仅直接威胁着职业工作人员的安全及健康,而且是构成环境放射性污染的最主要的现实的和潜在的污染源。对放射性废物的管理则是核工业,核电站等安全工作中的重要组成部分,是发展核科学与工程的先决条件之一,同时还是环境科学的一个重要分支学科。作好放射性废物管理工作,对保护环境和人类健康、促进核科学的发展及应用有重要意义。     

核设施退役中若干环境相关问题的探讨

核设施退役有利于消除核安全隐患,减少辐射环境风险,是环境保护的一项重要活动。本文讨论了在核设施退役过程中应重点关注的几个问题:退役目标和剂量约束值、退役过程中有关控制值的制定、放射性废物管理以及退役过程中和退役终态的监测。并结合退役项目说明了在退役实施中应该重点关注的环境相关问题。     

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。     

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.     

Safety requirements for the design of large containers for decommissioning waste

About 50% of the total volume of conditioned radioactive waste from nuclear power generation will finally result from the decommissioning of nuclear power plants (NPPs). Higher activated metallic waste from the core region of the reactors would, according to the International Transport Regulations (IAEA), require a type B container. This would, however, bring a significant increase in the costs of the management of such waste. A considerably cheaper solution of this problem can be achieved by separating the protection requirements for type B packaging (i.e. mechanical integrity and tightness). By using industrial packaging (IP) designed for a higher mechanical integrity, it is possible to cope with higher IAEA protection goals for the safe transport of dismantling waste without strictly following the extremely high and also expensive tightness requirements for type B packaging. This is because the radioactivity is bound in the metallic lattice of such activated decommissioning waste.The above mentioned strong IP for decommissioning waste can also be used for other highly activated waste from the core region (e.g. fuel element boxes, control rods or other activated equipment) during the operation of the NPPs.     

经合组织核能署放射性废物管理和退役活动概述

经济合作与发展组织(简称经合组织)核能署(OECD/NEA)放射性废物管理委员会协助各成员国制定各类放射性废物和乏燃料的长期管理战略,在监管、安全全过程系统分析、与利益相关方的沟通、非常规和遗留废物表征方法学、核设施退役的技术和成本估算等方面开展前沿研究。中国已成为全球在建核电机组最多的国家,在放射性废物管理和退役的技术、利益相关方沟通、成本优化等方面面临很多挑战。中国加强与核能署的交流合作,有助于实现放射性废物的安全处理处置,推动核电“走出去”的国家战略。     

Improved analytical methodology for calculation assessment of material parameters in the nuclear installation decommissioning process

The process of nuclear installation decommissioning is, besides other features, characterized by production of large amount of various radioactive and non-radioactive materials or waste that have to be managed, taking into account its physical, chemical, toxic and radiological characteristics. Waste management is considered to be one of the key issues within the frame of the decommissioning process from the technological and also financial point of view. Because of that mentioned fact, the evaluation of costs and other parameters is necessary to be done as precise as possible in the decommissioning planning period. The calculation code OMEGA with its implemented module of integrated material flow, is suitable for the assessment and further optimization of the various decommissioning waste management scenarios considering the different input parameters.In the paper, the improved analytical methodology based on the identification of decommissioning materials, definition of detailed material streams, development of scenarios, calculation of output parameters and final optimization, is presented. The process of implementation of such methodology to the existing OMEGA material flow system, including the new or perspective technologies and methods for the waste managing, is also discussed more in details.Finally, the summarizing conclusions and recommendations resulting from the model calculation results, done for the verifying the suggested methodology and functionality of new improved material flow system of the OMEGA code, are presented.     

核电厂退役资金管理

核电厂退役资金问题是核电政策、核电管理、退役管理方面的重要问题之一。文章介绍了国外核电厂退役现状,对国外在核电厂退役费用估算、资金提取和管理、保证资金充分性等方面的实践进行了阐述;在简要分析我国核电厂退役资金管理现状的基础上,提出了当前在退役资金方面需要开展的工作。     

Developing Integrated Decommissioning Information Management System (IDIMS) of Nuclear Facilities

In Taiwan, the Taiwan Research Reactor (TRR) was shut down in January 1988, and a few nuclear facilities were accompanied to stop operation within Institute of Nuclear Energy Research (INER). For public health and safety reasons, INER dismantled step by step its expired nuclear facilities. Integrated Decommissioning Information Management System (IDIMS) was developed to ensure safety of dismantling and to record all activity data during the decommissioning project. These recorded activity data range from data of planning, licensing, post-operation to those of radioactive waste management and storage. In addition, IDIMS was expected to preserve decommissioning knowledge using information technology from practical data and problem solving. It also is anticipated that IDIMS will be an important knowledge repository and design base for decommissioning projects of nuclear power plants in Taiwan.     

核设施运行及退役中的废物最小化技术

核设施的运行及退役不可避免会产生放射性废物,废物管理的代价以及对公众、工作人员和对环境的危害取决于废物的数量及废物中所含的放射性核素,在核燃料循环过程中进行废物最小化管理是降低这些影响的一项必须的活动。在有些国家,废物最小化已作为一项国策。本文介绍了放射性废物最小化的环境效益及核设施运行和退役过程中废物最小化的方法,重点介绍了已研发的部分有效的废物最小化技术。通过总结美国等发达国家的放射性废物最小化的经验,提出了如何在我国实现放射性废物最小化的建议。     

A study of the decommissioning procedure of an activated structure through an evaluation of the decommissioning cost for a research reactor

As decommissioning of a research reactor and a nuclear installation requires a long period of time from the decommissioning preparation work to the site remediation, the management of the data generated during the entire period of decommissioning is one of the most important tasks. In particular, the data obtained from research reactor decontamination and decommissioning activities can be important resources securing the safety and economic feasibility for other research reactor decommissioning. The owner of the research reactor and nuclear power plant need to submit decommissioning plan to the regulatory body at the starting stage of the research reactor and nuclear installation decommissioning project. The cost plan for decommissioning and the method for assessing the amount of exposure to protect workers must be stated in the decommissioning plan.This paper introduces the DES (Decommissioning Engineering System) that can be able to manage the data generated in the process of decommissioning of the TRIGA research reactor, to calculate an amount of waste, to evaluate decommissioning cost after deriving unit work productivity factor, and to predict the decommissioning process in advance. To verify the usability of this system and data integrity through connections among the unit systems, it describes the process to calculate the decommissioning cost using the data generated in dismantling an activated bio-shielding concrete in the TRIGA research reactor.As a result of the experiment to calculate the decommissioning cost with the TRIGA research reactor structure, it was found that the calculations were done precisely without flaw as the purpose of the experiment. Therefore, the DES can not only be used for other research reactors decommissioning, but also it is expected to be applied to other research reactors in the future. As a decommissioning cost between an activated concrete and a non-activated concrete according to the method of the dismantling procedure was significantly different, a study regarding the dismantling procedure needs more research.