放射性废物冷坩埚玻璃固化技术发展分析

冷坩埚技术作为第四代玻璃固化工艺,已成为最有应用前景的玻璃固化技术。本文阐述了冷坩埚技术的原理及应用特点,概述了国际冷坩埚玻璃固化技术研发现状,并对其涉及的关键技术进行了分析,在此基础上提出了我国发展冷坩埚技术的设想。     

冷坩埚玻璃固化技术及应用

介绍了法国、韩国、俄罗斯冷坩埚玻璃固化技术在核领域中的研究与工程应用,以期为我国冷坩埚技术的开展提供借鉴和参考。     

放射性废物无机固化处理技术

【日本《原子力工业》1988年第8期第31页报道】核电站的运行和维修保养产生各种放射性废物。这些废物按形态可分为气体、液体和固体三类。其中固体废物大体上又可分为废液固化体和混杂固体。所谓废液固化体是指将液体废液中不能重复利用的部分经浓缩并用水泥、沥青或塑料等进行固化处理后用容器封装而成的固化体。混杂固体     

冷坩埚技术处理动力堆乏燃料高放废液的应用前景分析北大核心CSCD

随着我国核电技术的发展,对动力堆乏燃料高放废液玻璃固化的需求变得越来越迫切。本文梳理了冷坩埚技术处理动力堆乏燃料高放废液的应用前景,针对冷坩埚在处理动力堆乏燃料高放废液方面的技术优势、设计优势以及工艺优势做出了详细阐述,并基于国外冷坩埚高放废液玻璃固化研究进展的分析,对冷坩埚技术未来发展提出了建议。     

卡尔斯鲁厄核研究中心放射性废物处理概况

卡尔斯鲁厄核研究中心(kfk)是联邦德国最大的综合性核研究单位,工作人员有近五千人。kfk设有废物去污部(HDB)负责放射性废物常规处理。本文就HDB的工作情况作一简要介绍。 1.设施HDB拥有的废物处理设施见表1。低放废液蒸发器采用强制循环压缩蒸发器,蒸汽压力1.4bar;中放废液蒸发器采用自然循环蒸发器,蒸汽压力2.5bar。蒸发浓缩     

冷坩埚玻璃固化启动过程数值分析

使用COMSOL有限元计算软件对熔池直径500 mm、高365 mm的电磁冷坩埚玻璃固化模型的启动过程进行了数值分析,研究了垂直方向环状启动加热块数量和位置分布对启动过程中加热速率、加热效率和温度分布的影响。计算结果表明,启动加热块距离坩埚底部250~300 mm时加热效率较高,增加垂直方向启动加热块的分布数量有利于在启动过程中加快升温速率、快速提高磁感应加热效率、加强玻璃熔体温度均匀程度和扩大玻璃熔体体积。     

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 …     

法国放射性废物焚烧技术

针对法国在放射性废物焚烧领域的研究成果,详细介绍了过量空气焚烧技术、固体废物焚烧技术、冷坩埚高温熔融技术的工艺流程及具体应用。     

放射性废物中Pu与^241Am的分离和测定

制定了从放射性饱和岩盐溶液中分离和测定微量Ｐｕ和＾２４１Ａｍ的方法。实验结果表明Ｐｕ的回收率为８５％，＾２４１Ａｍ的回收率为９０％。此法适宜于放射性核素在岩盐地质层迁移的研究中对Ｐｕ与＾２４１Ａｍ的测定。     

Waste management scenario in the hot cell and waste storage for DEMO

Management strategy of radioactive waste generated in periodic replacement may be important in the point of view of fusion reactor design, because it has a large impact on the design of the hot cell and waste storage in the plant. In the replacement period of a fusion power reactor, the assembly of blanket or divertor modules needs to be removed from the reactor in order to minimize remote maintenance in the vacuum vessel and to attain reasonable plant availability. In the hot cell, the modules will be removed from the back plate of the assembly. Here, note that the active cooling must be done by a way that does not cause contamination of the hot cell environment due to dispersion of tritium and tungsten dust. In this sense, the cooling scenario is adopted that the existing pipe of cooling water in the assembly is connected to a different cooling water system in the hot cell. On the other hand, it is assumed that the structural material (F82H) of the blanket and divertor is not recycled due to its high contact dose rate. It should be crushed into small pieces to reduce volume of the waste and required storage space. In this paper, the basic idea of the waste management scenario and the conceptual design in the hot cell and waste storage for DEMO has been proposed.     

桶装核废物的非破坏性分析(续)

有源γ射线(X射线)法可进一步分为吸收谱(吸收测量)法和有源诱发射线法。吸收谱法的分析原理是：当一定量的射线透射样品时,样品内的各元素具有正好吸收某一能量的射线的特性,从而使透射的射线强度大大减弱,这种减弱的多少与该元素的含量有关,这一现象称为     

Corrosion study of a highly durable electrolyzer based on cold crucible technique for pyrochemical reprocessing of spent nuclear oxide fuel

The application of the cold crucible technique to a pyrochemical electrolyzer used in the oxide-electrowinning method, which is a method for the pyrochemical reprocessing of spent nuclear oxide fuel, is proposed as a means for improving corrosion resistance. The electrolyzer suffers from a severe corrosion environment consisting of molten salt and corrosive gas. In this study, corrosion tests for several metals in molten 2CsCl–NaCl at 923 K with purging chlorine gas were conducted under controlled material temperature conditions. The results revealed that the corrosion rates of several materials were significantly decreased by the material cooling effect. In particular, Hastelloy C-22 showed excellent corrosion resistance with a corrosion rate of just under 0.01 mm/y in both molten salt and vapor phases by controlling the material surface at 473 K. Finally, an engineering-scale crucible composed of Hastelloy C-22 was manufactured to demonstrate the basic function of the cold crucible. The cold crucible induction melting system with the new concept Hastelloy crucible showed good compatibility with respect to its heating and cooling performances.     

Recovery of minor actinides from spent molten salt waste and decontamination of molten salt waste

Recovery of minor actinides from spent molten salt is one of the important issues. Decontamination of spent molten salt waste is also the problem to be solved for establishment of pyrochemical reprocessing. The decontamination method of spent molten salt waste with recovery of minor actinides has been proposed. Our proposed process is based on the hydrometallurgical process. This process consists of the following processes. First, the spent molten salt waste is dissolved in aqueous solution. Next, the minor actinides are recovered by chromatographic techniques using the pyridine resin in the methanolic hydrochloric acid solution. In the last process, the spent molten salt waste is decontaminated by the cation-exchange chromatography. In the present paper, the adsorption behavior of minor actinides, rare earth elements, alkaline earth elements, and alkali metal elements on pyridine resin is reported. The demonstration experiment of the recovery of the minor actinides from simulant spent molten salt waste is also reported.     

几种高选择性无机离子交换剂在放射性废水处理中的应用

介绍了铯离子交换剂、锶离子交换剂和钴离子交换剂的特性、水处理运行条件、选择性吸附交换能力及其在放射性废水处理中的应用。     

无机离子交换材料在放射性废水处理中的应用

综述了用于放射性废水处理的各种无机离子交换材料及其应用,包括沸石、复合离子交换剂、金属亚铁氰化物及铁氰化物、杂多酸盐、多价金属磷酸盐、多价金属（过渡金属）的水合氧化物和氢氧化物、以及两种新型多孔材料——钛硅酸盐晶体和原子簇化合物。以期对我国新型无机离子交换材料的研究有所帮助。     

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.