放射性废物的焚烧处理

本文论述了放射性废物焚烧处理的意义、焚烧工艺、设计考虑和发展动态，并对发展我国放射性废物焚烧技术进行了讨论。     

关于城市放射性废物管理

本文探讨了城市放射性废物的管理问题。城市放射性废物按其来源可分为医疗、生物和非生物研究废物三类,具有分散、数量少和活度低的特点。建议使用统一的废物包装器收集城市放射性废物,利用公共垃圾处置场处置部分放射性固体废物,对废闪烁液的处置建议采用下水道排放或焚烧。     

瑞典核电站反应堆废物管理

本文介绍了瑞典核电站反应堆废物的处理方法、中间贮存、运输、最终处置和管理费用等情况。     

低水平放射性废物和混合废物的商用处理技术（三）

４．２　压缩压缩是一种机械减容方法,用于处置前减少废物的总体积,这是通过对废物实施高压以减少空隙来实现的。这里提供的压缩和打包技术在核工业中已被采用。压缩技术所用的主要设备是压实机系统。该系统中有一个压力机,它采用水平或垂直的压头,将压力作用于桶式或箱式容器中的废物上。在压缩过程中完成的减容是废物空隙空间、施加的压力、废物的堆密度及其弹性特征的函数,减容系数一般在３～１０之间。决定压实机大小和功率要求的参数包括处理量、废物类型、被压缩物件的大小规格、处置容器的规格、以及要求的减容效果。在核工业中…     

意大利放射性废物管理活动

意大利管理和审批局(Italin Reglation and Licensing Body)于1987年发布了技术导则26(Technical Guide 26),规定了放射性废物管理原则,确定了为满足处置条件,放射性废物处理所需达到的最低要求。目前,意大利将放射性废物分成三类:(1)经过几个月至几年,衰变达到豁免值,     

铀矿开采废物最小化技术

介绍了铀矿开采废物的组成,重点分析了铀矿山采矿废物最小化管理技术,并给出了加拿大和法国废物最小化管理的实例。     

比利时放射性废物管理简介

本文介绍了比利时放射性废物管理的体系，目前开展的主要工作等。     

放射性废物管理的现状和展望

本文概述了我国放射性废物管理的现状。对今后放射性废物的管理战略、管理的法规和标准体系、管理机构及处置技术等方面提出了建议。     

田湾核电基地废物最小化

田湾核电基地目前有4台WWER核电机组和两台M310改进型核电机组。为了降低待处置固体废物包产生量,满足废物最小化管理目标,田湾核电基地在从源头减少放射性废物的同时,建造了6台机组共用的放射性废物处理中心。采用烘干、超级压实和水泥固定工艺处理放射性废物,配合采用混凝土高完整性容器,在废物包满足近地表处置要求的前提下,各机组每年需要处置的废物量不超过50 m³。具有良好的经济效益和社会效益,对多堆核电厂址的废物最小化有一定的借鉴意义。     

放射性废物的最少化

本文介绍了放射性废物最少化的意义和措施,总结了核电厂实现废物最少化的方法和作用,介绍了法国和美国废物最少化的经验。     

Radioactive waste management practices in India

Concern for the environment and establishment of radiation protection goals have been among the major priorities in planning of India's nuclear energy programme. In the Indian nuclear fuel cycle, right from inception, a closed loop option has been adopted where spent fuel is reprocessed to recover plutonium and unused uranium. The emphasis has been to recover actinides, individual fission products and recycle them back to the fuel cycle or use them for various industrial applications. The development of innovative treatment processes for low and intermediate level wastes in recent times has focused on volume reduction as one of the main objectives. In the case of high-level liquid waste, vitrification in borosilicate matrix is being practiced using induction heated metallic melters at industrial scale plants at Tarapur and Trombay.Currently, there are seven operating near surface disposal facilities co-located with power/research reactors in various parts of the country for disposal of low and intermediate level solid wastes. These are routinely subjected to monitoring and safety/performance assessment. An interim storage facility is operational for the storage of vitrified high-level waste overpacks for 30 years or more. Nation wide screening of potential regions and evaluation of rock mass characteristics is in progress for ongoing geological repository programme. Preliminary design and layout of an underground research laboratory/repository has also been initiated.A research programme is underway for long-term evaluation of vitrified waste product under simulated repository conditions. Research is also directed towards development of advanced technologies for waste processing as well as conditioning in vitreous and ceramic matrices. The Department of Atomic Energy with participation of the Indian industry has developed all essential remote-handling gadgets required for operation and maintenance of waste management system and assemblies including decommissioning.     

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.     

Requirements on waste packages resulting from mechanical and thermal impact during the operational phase of a waste repository

The aim of the disposal of radioactive waste is the protection of man and environment during the operational and the post-operational phase from the ionizing radiation of the radionuclides contained in the waste. In order to ensure this protection goal requirements are derived for the design of the repository as well as for the radioactive waste to be disposed of.The technical requirements for the design of the plant include for example the closing-off structure of filled emplacement rooms. The requirements for waste packages derived from safety analysis are related to the activity inventory, the waste form and the packaging. The type and extent of these requirements are described and it is shown on which safety aspects they are basedAs an example the radioactive waste with negligible heat generation is considered. The requirements on six different waste forms and on two waste classes of the packaging result from the mechanical and thermal impact during normal operation and in the case of incidents and serve as a base for the conditioning of the radioactive waste. Moreover, the way in which the properties of the waste form and the packaging are taken into account in the long-term safety analysis is described.     

Environmental and economic vision of plasma treatment of waste in Makkah

An environmental and economic assessment of the development of a plasma-chemical reactor equipped with plasma torches for the environmentally friendly treatment of waste streams by plasma is outlined with a view to the chemical and energetic valorization of the sustainability in the Kingdom of Saudi Arabia(KSA). This is especially applicable in the pilgrimage season in the city of Makkah, which is a major challenge since the amount of waste was estimated at about 750 thousand tons through Arabic Year 1435 H(2015), and is growing at a rate of 3%–5% annually. According to statistics, the value of waste in Saudi Arabia ranges between 8 and 9 billion EUR. The Plasma-Treatment Project(PTP) encompasses the direct plasma treatment of all types of waste(from source and landfill), as well as an environmental vision and economic evaluation of the use of the gas produced for fuel and electricity production in KSA, especially in the pilgrimage season in the holy city Makkah. The electrical power required for the plasmatreatment process is estimated at 5000 kW(2000 kW used for the operation of the system and 3000 kW sold), taking into account the fact that:(1) the processing capacity of solid waste is 100 tons per day(2) and the sale of electricity amounts to 23.8 MW at 0.18 EUR per kWh.(3) The profit from the sale of electricity per year is estimated at 3.27 million EUR and the estimated profit of solid-waste treatment amounts to 6 million EUR per year and(4) the gross profit per ton of solid waste totals 8 million EUR per year. The present article introduces the first stage of the PTP, in Makkah in the pilgrimage season, which consists of five stages:(1) study and treatment of waste streams,(2) slaughterhouse waste treatment,(3) treatment of refuse-derived fuel,(4)treatment of car tires and(5) treatment of slag(the fifth stage associated with each stage from the four previous stages).     

高放废物地质处置库花岗岩体预选研究

简要介绍了应用遥感技术结合地质研究,优选高放废物地质处置库花岗岩体的思路和方法.以北山外围地区为例,通过遥感数据处理,遥感影像解译,岩体地质特征分析,岩体预选准则的建立,在野外勘查的基础上,预选了若干有利的花岗岩体.为优选高放废物地质处置库场址提供决策依据.     

放射性废水远红外蒸发处理装置研制

为解决现有可移动式废水处理装置无法处理含盐量高、含油量高的放射性废水, 以及净化系数不高等问题,基于远红外蒸发处理技术研发了一套移动式放射性废水处理装置。装置主要由运输车、保温舱、废水处理系统、控制系统及外部管路组成,具有可移动、净化系数高、 适用性强等优点。本装置设计处理能力为24 L/h,蒸残液最大含盐量为300 g/L。冷调试结果表明装置设计安全可靠,结构合理,性能稳定,满足设计要求。     

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.     

气隙式膜蒸馏处理低放废液

低放废液在放射性废液里占有很大的比例,我国制定了严格的排放标准,尤其是对内陆核电站,需要选择更高效的处理技术,有必要研究膜蒸馏处理低放废液后的净化效果。基于气隙式膜蒸馏装置研究对模拟低放废水中微量的Sr~(2+)和Cs+的净化效果,以及温差和流速对净化效果的影响,对某乏燃料后处理厂里的低放废液进行处理。结果表明:膜蒸馏装置对微量的Sr~(2+)和Cs+平均截留率均大于99.99%,去污因子可以达到104量级以上;流速和温差对膜蒸馏装置的净化效果基本没有影响;对没有进行任何预处理后处理厂的低放废液,膜蒸馏装置连续处理4天多,处理后的馏出液的平均总α活度浓度为0.04Bq/L,平均总β活度浓度为15.13Bq/L,远低于该厂的排放标准。     

Tritium analysis in hydraulic oil waste by oxidation technique

The aim of the present study is to investigate a method to evaluate the tritium activity in hydraulic oil waste generated during the operation of Romanian Cernavoda Nuclear Power Plant.The method is based on a combustion technique using the 307 PerkinElmer^® Sample Oxidizer model.The hydraulic oil samples must be processed prior to counting to avoid color quenching (the largest source of inaccuracy) because these samples absorb in the region of 200–500 nm, where scintillation phosphors emit.Prior to combustion of the hydraulic oil waste, tritium recovery degree and tritium retention degree in the circuits of combustion system were evaluated as higher than 98% and less than 0.08%, respectively.After combustion, tritium activity was measured by a 2100 Tri-Carb^® Packard model liquid scintillation analyzer.The blank counts were 16.25 ± 0.50 counts/min, measured for 60 min. The significant activity level value was 6.53 counts/min, at a preselected confidence level of 95%. The Minimum Detectable Activity of a 0.2 mL hydraulic oil sample was calculated to 1.09 Bq/mL. Therefore, the developed method is sensitive enough for the tritium evaluation in the ordinary hydraulic oil waste samples.     

江苏省城市放废库辐射环境监测水平研究北大核心CSCD

随着核技术在各领域的广泛应用,辐射环境的安全受到越来越多的重视。以江苏省城市放废库为研究对象,从2015年起连续对放废库进行辐射环境监测6年。对放废库周围的γ辐射空气吸收剂量率,水源水中总α、总β以及土壤中放射性核素进行了监测,并对辐射监测结果进行了分析。研究结果表明γ辐射空气吸收剂量率敏感点范围为59.0~96.5 nGy/h,源库四周范围为81.92~103.32 nGy/h;水源的总α和总β范围分别为0.90×10^(-2)~5.87×10^(-2)Bq/L和3.00×10^(-2)~16.00×10^(-2)Bq/L。γ辐射空气吸收剂量率的变化主要与源库的距离和废源的管理有关;水体中放射性水平变化主要与年降水量有关;土壤中核素的变化主要与放射性气溶胶有关。所有变化均在本底范围内涨落,对环境几乎没有影响,可以确保辐射环境安全。