亚洲核安全网络放射性废物专题会议暨乏燃料管理安全与放射性废物管理安全联合公约研讨会

2007年9月3日～9月7日,国际原子能机构（nEA）在澳大利亚悉尼组织召开了“亚洲核安全网络放射性废物专题会议暨乏燃料管理安全与放射性废物管理安全联合公约（JC）研讨会”。受会议主办方IAEA和承办方澳大利亚核科学和技术中心（ANSTO）的邀请,国家环境保护总局国际合作司黄萍和中国辐射防护研究院三废治理研究所范智文参加了此次会议。     

《放射性废物安全公约》生效

【日本《原子能产业新闻》2001年3月29日报道】 国际原子能机构(IAEA)于2001年3月20日宣布,与乏燃料及放射性废物管理与贮存的安全性相关的第一个国际性公约——《放射性废物安全公约》于2001年6月18日生效。 1997年9月15日,该公约在IAEA外交会议上获得通过,从同年的IAEA大会开始开放供签署。在获得包括拥有运行中的核电站的15个国家在内的25个国家批准90天后,公约生效。爱尔兰为第25个批准国。 该公约适用于乏燃料安全管理即“除厂内运输外的所有乏燃料处理、贮存活动”;此外,还适用于放射性废物安全管理,包括整、贮存/处置等一切活…     

美国关于核废物管理国际合作的基本考虑

确保乏燃料与放射性废物安全的最终责任应由国家承担。最新的动向是，在乏燃料和放射性废物的安全有效管理方面有了进展，即通过国家间的协议，使一国设施的应用能分惠于其他国家。总的说来。美国赞成一个地区内的各国携起手来共同解决其核废物问题，尽管关于区域处置库的任何提案均必须对其自身优缺点进行逐一评价。国际原子能机构(IAEA)和《乏燃料管理安全与放射性废物安全公约》建立了放射性废物和乏燃料转移的有关技术规范，但还存在一些政治上的考虑，而这些考虑最终还必须由国家来决策。     

IAEA“放射性废物管理专题组第4次年度会议”简介

2009年9月28-30日,受国际原子能机构（IAEA）及中国国家原子能机构（CAEA）的委托,中国辐射防护研究院在山西省太原市承办了“放射性废物管理专题组（RWMTG）年度会议”和“亚洲核安全网络（ANSN）框架下从最近召开的‘联合公约’审议会议汲取的经验教训讲习班”。     

加拿大稳步推进废物管理工作

<正>【本刊2015年2月综合报道】加拿大核安全委员会(CNSC)2015年1月22日公布了署期为2014年10月的《乏燃料和放射性废物安全管理联合公约加拿大国家报告》。这份报告是加公布的第五份类似报告。加拿大核废物管理组织(NWMO)同日宣布将在4个地区继续推进乏燃料深层地质处置库的选址工作。国家报告核安会公布的第五份国家报告介绍了自第四份国家报告发布以来加在乏燃料和     

国际公约现状

【《国际原子能机构通报》第 40卷第 2期报道】　目前世界上愈来愈多的国家加入在国际原子能机构 (IAEA)主持下通过的国际公约。　　 ● 《核安全公约》。 1998年 ,又有 4个国家 ,即意大利 (1998年 4月 15日批准 )、葡萄牙 (1998年 5月 2 0日批准 )、摩尔多瓦共和国 (1998年 5月 7日加入 )和乌克兰 (1998年 4月 8日批准 ) ,同意受该公约约束。截至19 98年 6月 ,该公约有 6 5个签字国和 46个缔约国。　　 ● 《乏燃料管理安全和放射性废物管理安全联合公约》。1998年 ,又有 9个国家签署该公约 ,和 3个国家批准该公约。它们是加拿大 (1998年…     

国际原子能机构(IAEA)安全标准概要北大核心CSCD

国际原子能机构(IAEA)的重要出版物之一是“安全标准”,为确保核安全提供基本原则、要求和建议。“安全标准”作为保护人和环境的全球参考,促进了全世界协调一致的高水平安全。诸如辐射的医疗应用,核装置的运行,放射性材料的生产、运输和使用,以及放射性废物管理等活动必须遵守安全标准。核安全的主要责任必须由负责这些活动的个人或组织承担。对安全进行监管是国家责任。     

国际放射性废物管理若干发展趋势

2002年12月召开了“国际放射性废物管理现状和发展趋势大会”。本文介绍了这次会议概况及有关进展，包括高放废物处置、乏燃料暂存、废放射源管理、NORM废物和放射性流出物排放控制等方面的进展。     

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。     

核燃料循环后端综合管理方案专题会议

在《乏燃料管理安全和放射性废物管理安全联合公约》缔约方第四次审议会议期间（2013年10月16至18日）,举行了不限人数工作组会议（OEWG）。在OEWG上,与会各缔约方一致认为：在第四次审议会议和随后的历次审议会议期间,针对某些特定议题,举行相应的专题会议十分重要。这些专题会议有助于缔约方之间就某些问题继续进行对话和沟通。     

Safety Standards for Radioactive Waste Management

Abstract

The International Atomic Energy Agency (IAEA) has established the Radioactiee Waste Safety Standards (RADWAS)) programme upon request by its Member States to provide evidence that radioactive waste can be managed safely. The RADWASS programme consists of a series of fifty-five internaiionll consensus documenss covering all parts of radioactive waste management, i.e. the subject areas:

Planning

Pre-disposal

Near surface disposal

Geological disposal

U/Th mining and milling

Decommissioning

A single Safety Fundamentals document will set out the basic safety principles for radioactive waste management. Each subject area is headed by a Safety Standard. Twenty-eight Safety Guides and twenty Safety Practices will provide further details for the implementation of safety requirements stated in the Safety Standards. The programme was started in 1991 and is being carried out in three phases (Phase I: 1991–1994; Phase II: 1995–1998; Phase III: post 1998). Phase I includes twelve documents comprising the Safety Fundamentals, four Safety Standards, five Safety Guides and two Safety Practices. The Safety Fundamentals and the Safety Standards are planned to be submitted to the Board of Governors for review and approval in 1994. Four of the Safety Guides have been or will soon be submitted for publication and the fifth will be finalised by the end of 1994. One Safety Practice on ‘Application of Exemption Principles’ was published at the end of 1992 and the second Safety Practice of Phase I is planned to be finalised in 1994. The thirty-seventh regular session gf the General Conference in the 361st plenary meeting adopted the resolution ‘Strengthening Nuclear Safety’ through the early conclusion of a Nuclear Safety Convention. It calls for ‘Measures to Strengthen International Co-operation in Matters Relating to Nuclear Safety and Radiological Protection’ and requests the Director General inter alia to initiate preparations for a convention on the safety of waste management as soon as the ongoing process of developing the RADW ASS Safety Fundamentals has resulted in broad international agreement. Approval of the document by the Board of Governors will be an important step toward convening the waste management Safety Convention. It is intended to finalise work on Phase I (1991–1994) documents by the end of 1994. Phase II envisages the initial preparation of thirteen documents comprising one Safety Standard, eleven Safety Guides and one Safety Practice. It is planned to start some of these activities in 1994.     

Regulatory control of the German radioactive waste management system

In Germany, all radioactive materials are controlled from their origin to their final disposal or release. This is in accordance with the IAEA draft Convention on the Safety of Radioactive Waste Management. A Waste Control System has been developed and is now available. Although the IAEA and EU regulations allow disposal outside the country of origin this philosophy is not in compliance with the present German disposal concept. As a consequence, Germany will not grant licences for the import of radioactive waste for final disposal or for export for disposal in a foreign country. Thus, unconditional clearance is a prerequisite if the final destination is outside Germany. However, Germany will closely follow all international developments in the field of radioactive waste disposal.     

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering, the studies related to risk analysis methodology, design, and operational management, physical phenomena, and emergency preparedness and nuclear security, have been progressed. Especially, ‘risk analysis methodology’ and ‘design and operational management’ are the main categories of the field, in which more than half of published articles on Journal of Nuclear Science and Technology are related to these categories.     

Independent Design Appraisal and Container Certification

Abstract

Under the IAEA Safety Series 6, waste and transport containers for radioactive materials must comply with specified standards of design, manufacture and test. In all cases, the consignor carries responsibility, but will generally neither design nor manufacture the container himself. Design appraisal, inspection during manufacture, and witnessing of tests by an independent third party can therefore be of benefit. In the case of ISO freight containers, such services can also incorporate Certification of containers as required by the International Container Safety Convention (CSC).     

国家核技术利用辐射安全管理系统数据接口的功能与设计

介绍了国家核技术利用辐射安全管理系统的主要功能与业务流程,根据地方环保部门自主建立的数据库的特点与使用情况,提出开发系统数据接口的意义及可行性,对数据接口设计的关键技术进行了分析。数据接口可以实现各数据库间的自动同步以及国家系统信息收集的智能化与自动化,可以避免用户在各系统中进行重复操作,可有效提高我国核技术利用辐射安全监管的办事效率和信息化水平。     

全国核与辐射安全监管信息系统的研究和建议

文章简要介绍了全国核与辐射安全监管信息系统的前期规划建设情况,包括基本建设内容、系统总体架构、以及工作中发现的影响和制约工作开展的主要问题,并提出了建议。     

熔盐堆的安全性介绍

介绍了四代反应堆的分类与特点,简述了第四代反应堆中唯一使用液态燃料的熔盐堆工作原理。基于与其他使用固体芯块燃料反应堆的比较,主要简述了熔盐堆更高的固有安全性特点,以及熔盐堆在燃料供应、废料最小化、防止核扩散诸方面的安全性优点以及熔盐堆发展面临的问题和挑战。说明了由于熔盐堆较高的工作温度使用布雷顿循环,提高热效率的优点。...     

核电厂安全管理工作探讨

搞好核电厂安全管理是核电厂安全生产的重要保证.核电厂安全管理包括建立健全安全责任制、安全生产的监督和管理及信息反馈、掌握安全防护规程、用科学态度处理放射性安全工作、保证工业安全及做好安全分析工作。我国核电刚刚起步,学习国外先进的安全规程,吸取他人的经验教训,探讨适合我国国情的安全管理规律是十分必要的.     

Safety assessment of the NET Predesign

Work carried out by European Associations on Safety and Environment inside the EC Fusion Technology Programme and by NET has been concentrated on safety-related guidance and on safety assessment of the NET Predesign. Emphasis has been put on analysis of accident sequences of regulatory concern up to worst case accidents, including quantification of consequences to components, systems, and plant, and of doses to the public. Probabilistic safety studies for the most important systems and broadly for the entire plant have been performed to supplement the calculated accidental doses by expectation values for their occurrence rate, and to check the relevance of the reference accident sequences selected initially by judgment. Waste masses per year of operation and for decommissioning have been quantified. For two countries and according to the practices and regulations of these countries, volumes of radioactive waste packaged for final disposal have been determined.Presented at the IAEA Technical Committee Meeting on Developments in Fusion Safety, Toronto, June 7–11, 1993.     

Management and Disposal of Waste from Fusion Power Reactors—Comparisons Between Different Blanket Designs

This paper gives results from a waste study performed for future fusion power station designs. The study has been carried out within the European Program on the Safety and Environmental Assessment of fusion power, Long-term (SEAL). Five different blanket designs were compared from the standpoint of waste. Results are given for comparisons regarding primary waste quantities, radiological hazards, chemical hazards, repository volumes required, and doses from repositories. The repository volumes required were compared for a hypothetical German scenario and the doses from repositories were compared for hypothetical French and Swedish scenarios.