核电厂放射性固体废物管理系统的研究与开发

目前我国在运核电厂和其他所有堆型（CPR1000、EPR和AP1000）的在建核电厂均缺少一套统一的放射性固体废物管理系统,缺乏对放射性固体废物从产生到最终处置的全周期跟踪管理。根据核电厂的放射性废物管理需求,研制了一套适合于各核电机型的核电厂放射性固体废物管理系统,对废物源项、处理、暂存、运输、处置全过程进行跟踪,使放射性废物管理安全、可控;研发了废物管理跟踪单和数据库,分析了废物管理工艺流程的逻辑关系,根据废树脂、浓缩液、废滤芯、检修废物等处理工艺分别设计了核素计算模型,可推算指定时刻的放射性水平,实现放射性废物数据的深度分析、应用以及对放射性废物安全管理的全过程追踪。研究成果已经在国内部分核电厂使用,有助于提高核电厂的放射性废物管理水平,具有较大的安全和社会意义。同时,该系统记录的数据有助于核电厂实现辐射防护优化设计和放射性废物最小化管理。     

Service-oriented architecture for an overall radioactive waste package record management system

In Taiwan, there are a few radioactive waste package record management systems independently implemented by radioactive waste generators, operators of waste management facilities, transport organizations and storage facilities. To claim compliance of a radioactive waste package record meets with waste acceptance criteria for disposal, an overall radioactive waste package record management system which records and tracks all relevant information, from raw waste characteristics, through changes related to waste processing, to final checking and verification of waste package parameters should be constructed in accordance with IAEA recommendation. Service-Oriented Architecture (SOA) is widely accepted as a new paradigm for integrating heterogeneous systems in an effective way. It has formed a new trend being adopted by organizations in mitigating legacy system problems as in to maximizing interoperability, reusability and flexibility. Based on the current radioactive waste management processes, this paper proposes a three-tier SOA for the further overall radioactive waste package record management system design.     

矿产资源开发利用放射性固体废物数据库管理系统

放射性核素会与一些矿产资源如锆、铁、独居石、钨、铍等伴生,随着矿产资源开采、精选、冶炼、加工过程,放射性核素会在不同的原料、中间产物、产品和废弃物中分离和富集,形成放射性废物。放射性废物会对人体和环境造成危害,为了保障放射性环境的生态安全,我们通过调研和实地检测后从基本理论、技术和管理等方面考虑,总结出矿产开发利用相关企业放射性废物管理的要求,开发出了一套放射性固体废物数据库管理系统,跟踪废物来源、放射性固体废物处置和回收利用的全过程,从而使放射性废料安全可控。同时分析了废弃物产生流程、处置流程、回收流程的逻辑关系,开发了废弃物基本信息、处置回收数据库和操作系统,并实现多厂地同时管理使用以及有关人员对各个厂地数据的查询和管理功能。该系统有助于提高矿产资源开发利用相关企业的放射性废物管理水平,对防治核辐射污染、实现辐射防护的优化设计和放射性废物的最小化管理有重大意义。     

Nuclear waste management in the US: The Nuclear Waste Technical Review Board's perspective

The US program for the management and disposal of commercial spent nuclear fuel and high level waste is in a period of potential programmatic, regulatory, and legislative change. Proposals currently being considered by the US Congress would authorize the development of a storage facility as soon as possible adjacent to the potential repository site at Yucca Mountain. The legislation also would establish regulatory requirements for a permanent repository at an individual dose limit of 1 mSv year⁻¹ (100 mrem year⁻¹) for the average person living near the repository. Concurrently, the fiscal year 1996 appropriation to characterize the Yucca Mountain site has been reduced by approximately 40%. These initiatives portend possible changes in the focus of the US program, including a fundamental shift in priority from permanent disposal to temporary storage, and a change in the approach to licensing a potential repository at the Yucca Mountain site. This paper provides the perspective of the members of the Nuclear Waste Technical Review Board on the impact these developments could have on the future of the US program. It discusses the Board's opinion on how to address the issues these and other developments raise in a way which moves the US civilian radioactive waste management program forward.     

What can a country with small nuclear program learn from other European countries?

In this paper the present status of the nuclear programme and radioactive waste management in Slovenia is briefly presented. The quantities of accumulated radioactive wastes are given and the storage capacities and plans and problems concerning the final disposal are described. Because of small nuclear programme and limited resources Slovenia cannot afford expensive research and development projects; therefore, in selecting the optimal long-term solution for its radioactive waste foreign experience and approaches are very important. Intercomparison of solutions in different areas of radioactive waste management in more developed countries can be of great help to such countries when the disposal programme is prepared, as is indicated in this paper.     

球床高温气冷堆核电站放射性废物最小化策略研究

放射性废物最小化是放射性废物管理的基本原则之一。高温气冷堆核电站放射性废物最小化策略研究对于优化设计与运行实践和全寿期放射性废物管理,以及高温气冷堆产业化发展具有重要意义。通过对世界上主要球床高温气冷堆运行历史和放射性废物数据的调研和论证,分析了球床高温气冷堆技术及其放射性废物特点,总结了高温气冷堆放射性废物管理值得借鉴经验及相关研究进展,提出了高温气冷堆核电站全寿期放射性废物最小化的策略和建议。     

Long term stability of iron for more than 1500 years indicated by archaeological samples from the Yamato 6th tumulus

One of the candidate materials for overpack in the Japanese engineered barrier system for high-level radioactive waste (HLW) is iron and therefore its long-term stability for at least 1000 years is very important for safety analysis of the repository system. Therefore, several of the iron artifacts excavated from the Yamato 6th tumulus (ancient tomb) in Nara prefecture were analyzed using X-ray computed tomography (CT) to determine corrosion depth. The samples analyzed, both of two large and 11 smaller iron artifacts are called ‘Tetsutei’. The thickness of each rust layer was measured from a cross-section image of the sample and the difference in material density between rust and iron was shown by the image density by the X-ray CT. In the case of pitting corrosion in the sample, the depth of the pits was measured directly and estimated as total corrosion depth with general corrosion layer. The corrosion depths are 0.5–2.1 mm. These data indicate conservative predictions for the extrapolations based on experimental studies. Such corrosion data from archaeological samples are useful in analogue studies of high-level radioactive waste disposal as evidence of long-term stability of a waste container.     

Regional system for registration and monitoring radioactive waste

A regional structure is proposed for the State registration and monitoring of radioactive waste for the Moscow region. Consideration is given to the problems, the information communications, the role of an interregional center for information analysis, and to solving the problem of the registration of radioactive waste as part of this system. An approach is proposed to monitoring the formation of waste which is based on ensuring conditions for not exceeding the temporary storage norms and for the correct time for removing radioactive waste. An algorithm is given for the efficient planning of its removal taking account of the requirements for radiation safety. Scientific-Production Association MosNPO “Radon”, Moscow. Translated from Atomnaya énergiya, Vol. 86, No. 6, pp. 465–470, June, 1999.     

Modelling of radioactive material release from waste packages in case of a fire event

Assumed incidents in the operational phase of the planned German repository Konrad for radioactive waste with negligible heat production were investigated in order to assess their possible radiological consequences. Release fractions of the radioactive substances contained in waste packages were assessed from experimental data obtained under thermal impact. They are given for halogens, tritium, ‘4C and other radionuclides and are classified according to the waste form groups and waste container classes.     

城市库废放射源治理工作中的剂量控制

城市放射性废物库废放射源治理过程中影响工作人员受照剂量的因素较多。为实现辐射防护的最优化,本文以全国城市库治理项目统计结果及现场实施经验为依据,分析了城市库废源的特点、辐射风险及剂量控制方法。并对城市库废源治理项目的剂量数据进行统计分析,发现剂量分布规律,为辐射防护工作提供指导和参考。     

Possible use of bisphenol-a polycarbonate in radioactive waste embedding

Frequent use of bisphenol-a polycarbonate in daily life results with a huge amount of polycarbonate waste. The proper utilization of this waste would be an environmental friendly approach. As polymeric materials are candidate materials for radioactive waste embedding, having an aromatic structure within the main chain, the bisphenol-a polycarbonate is a candidate material to be used as an embedding matrix for the confinement of low and intermediate level radioactive waste. This possibility would partly solve the problem of huge amount of waste generated due to the usage of polycarbonate.In this study, the possibility for the usage of bisphenol-a polycarbonate in radioactive waste management was investigated regarding to radiation stability and resistance. For that purpose, changes in the properties of polycarbonate irradiated with different doses were determined. Irradiations, which were carried out for the duration of more than 8 months with an initial dose rate of 993 Gy/h, ended with a total irradiation dose of 4341 kGy to the samples. A detailed characterization of irradiated polycarbonate samples were performed by tensile, DMA, TGA, ATR-FTIR, AFM, EDX and SEM tests. The modifications within the polymer matrix have been reported. The total dose at which bisphenol-a polycarbonate could resist regarding to mechanical properties was determined.     

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。     

对法国高放废物处置安全审评的分析研究

介绍了法国高放废物处置研究现状和规划,对法国高放处置场的审评技术单位法国核与辐射安全研究院（IRSN）所开展的高放处置安全研究和审评工作及其提出的审评原则和审评要点进行了分析研究,并对我国的高放处置安全审评工作提出了建议。     

放射性废物管理中值得关注的一些新概念

本文介绍了国际原子能机构及国际放射防护委员会近年来在放射性废物管理领域提出的一些新概念。诸如对放射性废物实行全过程管理；对长寿命固体放射性废物处置的安全评价采用有约束的最优化办法，并且指出最优化是一个判断过程等。本文用意在于引起同行对这些概念的注意和重视，以便对放射性废物的安全管理有所帮助。     

Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice.The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.     

Radwaste Management and Transport in the Republic of Croatia — Present Status and Main Issues

Abstract

Radioactive waste in Croatia is generated from various nuclear applications as well as from the Kr?ko NPP (a joint venture Slovenian and Croatian facility). The national programme on radioactive waste management is aimed at straightening existing infrastructure in the field, establishing a new and more transparent system of responsibilities as well as developing new legislation. The siting of the LLW/ILW repository in the Repubic of Croatia is one of the most important steps in the whole radioactive waste management cycle. A review of the main activities, the role of institutions involved and some on-going projects which cover the present situation in the field of radioactive waste management in Croatia are presented.     

Recent advances in fusion radioactive material studies

This paper focuses on a few recent advances and research developments concerning fusion radioactive waste management studies. In particular: the role of fusion power in the frame of the future production of nuclear radioactive waste, in terms of potential waste avoidance using a precautionary fusion waste management policy, activation of W and its alloys (examining and comparing the activation of W-based components in ITER, PPCS, and ARIES designs), development of a management strategy for activated materials from complex components (such as blanket and divertor), waste decay heat and maintenance questions, materials detritiation, and public acceptance of clearable and recyclable materials.     

Nuclear fuel cycle strategies including Partitioning and Transmutation

The widespread concern about radioactive waste management has promoted interest during the last decade for the potential role of Partitioning and Transmutation strategies, in order to alleviate the burden on future deep geological repositories. The physics of transmutation allows to point-out preferential approaches, e.g., based on the use of a fast neutron spectrum. The practical implementation of Partitioning and Transmutation implies the development of sophisticated technologies and can be more realistic if seen in a regional context. Some examples will be given to illustrate the “regional” approach, and some considerations will be made on the use of Accelerator Driven Systems (ADS), in the frame of a progressive strategy from present nuclear power fleets to future systems, as studied, e.g., in the frame of the GENERATION-IV initiative.     

Cement mortar-degraded spinney waste composite as a matrix for immobilizing some low and intermediate level radioactive wastes: Consistency under frost attack

The increasing amounts of spinning waste fibers generated from cotton fabrication are problematic subject. Simultaneous shortage in the landfill disposal space is also the most problem associated with dumping of these wastes. Cement mortar composite was developed by hydrating mortar components using the waste slurry obtained from wet oxidative degradation of these spinney wastes. The consistency of obtained composite was determined under freeze–thaw events. Frost resistance was assessed for the mortar composite specimens by evaluating its compressive strength, apparent porosity and mass loss at the end of each period of freeze–thaw up to 45 cycles. Scanning electron microscopy, infrared spectroscopy and X-ray diffraction analyses were performed for samples subjected to frost attack aiming at evaluating the cement mortar in the presence of degraded spinney waste. The cement mortar composite exhibits acceptable resistance and durability against the freeze–thaw treatment that could be chosen in radioactive waste management as immobilizing agent for some low and intermediate level radioactive wastes.