标准编号:	HAD 401/08-2016
中文名称:	核设施放射性废物最小化
英文名称:	Minimization of Radioactive Waste in Nuclear Facilities
行业分类:	HAD    核电行业标准
发布机构:	国家核安全局
发布日期:	2016-10-21
实施日期:	2016-10-21
标准状态:	valid
翻译语言:	英文
文件格式:	PDF
中文字符数:	15000 字
翻译价格(元):	2250.0
交付时间:	付款后 1 个工作日

1 Introduction 1.1 Purpose This guide provides guidance for the units responsible for design, construction, operation and decommissioning of nuclear facilities to carry out radioactive waste minimization (hereinafter referred to as “waste minimization”), and also provides reference for regulatory authorities to conduct nuclear safety review, supervision and management. Appendixes I, II and III have the equal force as the text. Annexes A, B and C are informative. 1.2 Scope This guide is mainly applicable to the waste minimization in the design, construction, operation and decommissioning stages of PWR nuclear power plants and it may also be referenced by nuclear facilities such as other reactor nuclear power plants, nuclear fuel cycle facilities and research reactors. 2 Objectives and principles 2.1 Overall objectives In the procedure of design, construction, operation and decommissioning of nuclear facilities, measures such as source control, recycling and reuse, clearance, optimized waste treatment and strengthened management are taken and cost and benefit analysis is conducted to enable the final amount of radioactive solid waste (volume and activity) as low as reasonably possible. 2.2 Basic principles The waste minimization of nuclear facilities shall be based on the premise of ensuring safety, with waste disposal as the core, and follow the principles of giving priority to source control, whole procedure management, all-member responsibility and continuous optimization for the purpose of realizing waste minimization through technical and management measures. 2.3 Target value of waste minimization The annual amount of radioactive solid waste from nuclear facilities shall be as low as reasonably possible by adopting practical design and management measures and comparing with international best practices. Annex A specifies requirements for annual amount of single-unit waste packages from PWR nuclear power plants in major nuclear energy countries in the world and waste packages from newly built PWR nuclear power units specified in nuclear power plant user requirement documents in US and Europe. 3 Waste minimization in design and construction stages 3.1 General requirements 3.1.1 Appropriate design measures shall be taken to reduce the generation of radioactive waste from the source and keep the amount of radioactive waste as low as reasonably possible. 3.1.2 Practical methods shall be taken to prevent the dispersal of radioactive contamination and the activation of materials. 3.1.3 Materials with less toxic and harmful components and easy for subsequent treatment are preferred to create conditions for waste minimization. Recycling technology shall be provided for reusable materials. 3.1.4 The target value of waste minimization in this stage shall be determined in combination with the construction planning of nuclear facilities at the plant site, by taking the safe treatment and disposal of waste as the objective, taking into account the radioactive waste treatment and storage facilities as a whole, and selecting safe and reliable advanced process technology and equipment for minimization. 3.1.5 Technical measures facilitating the decommissioning of facilities and realizing the minimization of decommissioned waste shall be taken. 3.1.6 Contents related to waste minimization shall be included in the safety analysis report of nuclear facilities. Appendix I specifies contents related waste minimization in the preliminary and final safety analysis reports of PWR nuclear power plants and it may be referenced by other nuclear facilities. 3.1.7 The nuclear facility design and construction units and construction contractors at all levels shall actively carry out training on waste minimization knowledge and skills, improve the quality of nuclear facility design, construction, installation and commissioning, and lay the foundation for safe operation of equipment and waste minimization in operation stage. 3.1.8 The design unit of nuclear facilities shall optimize the design scheme and promote the continuous improvement of waste minimization in combination with the development of waste minimization technology and the feedback of operation experience at home and abroad. 3.2 Reduce the generation of radioactive waste from the source Taking PWR nuclear power plants as an example, the method of reducing radioactive waste from the source is given below, which may also be referenced by other nuclear facilities. 3.2.1 System design 3.2.1.1 The amount of radioactive waste shall be reduced by adopting long-term fuel cycle and improving the availability (load factors) of nuclear power plants. 3.2.1.2 The reactor coolant to be charged and discharged and the amount of liquid waste to be treated later can be reduced by optimizing the design (such as using control rods instead of adjusting reactivity by changing boron concentration of reactor coolant). 3.2.1.3 The dispersal of radioactive contamination may be prevented by taking measures such as setting radiation area reasonably, organizing airflow and material flow direction reasonably, and setting up radioactive contamination monitoring devices. 3.2.1.4 The quantity of equipment, pipes and valves can be determined reasonably by optimizing the design. 3.2.1.5 The sealing property of the system containing radioactive materials shall be improved to reduce the leakage of radioactive substances. 3.2.1.6 The corrosion-resistant and irradiation-resistant coating or steel linear shall be applied to the surface of concrete and other materials that may be radioactively contaminated. 3.2.1.7 The steam generator sewage, nuclear island ventilation system condensate and conventional island liquid effluent must be collected and monitored for discharge; if the analyzed radioactive activity concentration exceeds the discharge control value, these effluents shall be sent to the liquid waste treatment system for treatment. 3.2.2 Selection of equipment 3.2.2.1 High-reliability fuel assemblies shall be adopted to improve the fuel cladding property and reduce the damage to fuel elements. 3.2.2.2 Equipment with high reliability, long service life and convenient for maintenance and repair shall be adopted to reduce the leakage of equipment and the waste generated during maintenance. 3.2.2.3 Advanced manufacturing process (such as acid cleaning and passivating of stainless steel surface and applying corrosion-resistant coating on carbon steel equipment) shall be adopted to reduce the corrosion of materials. 3.2.3 Selection of materials 3.2.3.1 Equipment, pipes and valves in contact with radioactive medium shall be made of appropriate stainless steel. Strictly limit the contents of cobalt, nickel, silver and other elements in the sealing materials of equipment, valves, pipes and gaskets in contact with the primary circuit coolant, antimony in the bearing materials of the main pump, and cobalt, nickel and other elements in the components and structural materials in the neutron accessible area of the reactor cavity radiation streaming, so as to reduce the generation of activated corrosion products. 3.2.3.2 For the quick connectors and valves in contact with radioactive medium, sealing materials capable of being used for a long time under certain medium environment conditions shall be adopted to reduce the frequency of corrosion, leakage and maintenance. 3.2.3.3 In the radioactive liquid treatment system, high-capacity resin shall be used to reduce the amount of waste resins. 3.2.4 Water chemistry control 3.2.4.1 The primary circuit water chemistry control shall be optimized by primary circuit hydrogenation, zinc injection, adding hydrogen peroxide before shutdown, and adopting effective purification technologies such as filtration, ion exchange and membrane technology to improve the coolant quality of primary circuit reactor and reduce the corrosion and erosion rate of primary circuit equipment. 3.2.4.2 The quality of primary circuit makeup water shall be improved to reduce the impurity content entering the active area of the core. 3.3 Design of radioactive waste treatment system Taking PWR nuclear power plants as an example, the following provides guidance for carrying out waste minimization in the design of radioactive waste treatment system, and may be referenced by other nuclear facilities. 3.3.1 Process design 3.3.1.1 Radioactive waste gases shall be collected and treated by classification according to their characteristics. 3.3.1.2 When the hydrogen-containing radioactive waste gas is subjected to storage and decay treatment, the number and volume of decay boxes shall be set reasonably according to the amount of waste gas (including overhaul conditions). 3.3.1.3 When the hydrogen-containing radioactive waste gas is subjected to activated carbon delayed treatment, the number of delayed beds and the loading capacity of activated carbon are reasonably determined. Activated carbon protected bed or other drying measures shall be taken to avoid the reduction of treatment efficiency or premature failure of activated carbon due to moisture. 3.3.1.4 Various radioactive liquid waste shall be collected by classification according to the physical, chemical and radioactive characteristics of radioactive liquid waste, especially the oily waste water, organic solvent, washing water containing detergent and shower water shall be collected separately from other liquid waste. 3.3.1.5 The leakage detection measures of radioactive liquid waste related systems shall be improved to find and eliminate leakage early. 3.3.1.6 The treatment process with high purification efficiency and generating less secondary waste shall be adopted according to the characteristics of various liquid waste. 3.3.1.7 The types and amount of chemicals added to various systems of nuclear power plants shall be evaluated and controlled strictly. 3.3.1.8 For cleaning and decontaminating of systems, equipment, components, appliances, radiation protection articles, walls and grounds, decontamination processes and detergents with high decontamination efficiency and generating less secondary waste shall be selected. 3.3.1.9 When the ion exchange desalination process is used to treat the process liquid waste that may contain colloids, the liquid waste should be pre-treated (flocculant injection and deep bed filtration, ultrafiltration, etc.). Filters shall be set before the ion exchange desalting bed and after the last stage of ion exchange desalting bed to intercept the suspended solids in the upstream wastewater and the resin chips leaked from the desalting bed.

1 Introduction 1.1 Purpose 1.2 Scope 2 Objectives and principles 2.1 Overall objectives 2.2 Basic principles 2.3 Target value of waste minimization 3 Waste minimization in design and construction stages 3.1 General requirements 3.2 Reduce the generation of radioactive waste from the source 3.3 Design of radioactive waste treatment system 4 Waste minimization in operation stage 4.1 General requirements 4.2 Waste minimization management measures 4.3 Continuous improvement of waste minimization 4.4 Requirements for waste minimization during safe shutdown of nuclear facilities 5 Waste minimization in decommissioning stage 5.1 General requirements 5.2 Waste minimization management measures 5.3 Waste minimization technology in decommissioning stage Terms and definitions Appendix I Contents related to waste minimization in the preliminary and final safety analysis reports of PWR nuclear power plant Appendix II Contents related to minimization of annual scrappage in operation stage of PWR nuclear power plant Appendix III Contents related to waste minimization in the decommissioning safety analysis report of PWR nuclear power plants Annex A Requirements for annual amount of single-unit waste packages from PWR nuclear power plants in major nuclear energy countries in the world and waste packages from newly built PWR nuclear power units specified in nuclear power plant user requirement documents in US and Europe Annex B Commonly used radioactive solid waste treatment technologies Annex C Good practice of waste minimization in nuclear power plants in China

1 引言 1.1 目的 本导则为核设施设计、建造、运行和退役单位开展放射性废物 最小化（以下简称废物最小化）工作提供指导，也为监管部门进行 核安全审评和监督管理提供参考。 附件Ⅰ、Ⅱ、Ⅲ与正文具有同等效力。 附录 A、B、C 为参考性文件。 1.2 范围 本导则主要适用于压水堆核电厂设计、建造、运行和退役阶段 的废物最小化，其他堆型核电厂、核燃料循环设施、研究堆等核设 施也可参考使用。 2 目标和原则 2.1 总体目标 在核设施设计、建造、运行和退役过程中，通过废物的源头控 制、再循环与再利用、清洁解控、优化废物处理和强化管理等措施， 经过代价利益分析，使最终放射性固体废物产生量（体积和活度） 可合理达到尽量低。 2.2 基本原则 核设施废物最小化应以确保安全为前提，以废物处置为核心， 通过技术和管理措施实现废物最小化，遵循源头控制优先、全过程 管理、全员责任和持续优化的原则。 2.3 废物最小化目标值 应通过采取切实可行的设计和管理措施，并与国际最佳实践相 比对，使得核设施放射性固体废物年产生量可合理达到尽量低。 附录 A 给出了世界主要核能国家压水堆核电厂单机组废物包年 产生量及美国和欧洲核电厂用户要求文件对新建压水堆核电机组废 物包年产生量要求。 3 设计和建造阶段废物最小化 3.1 一般要求 3.1.1 应通过合适的设计措施，从源头减少放射性废物的产生， 使放射性废物产生量可合理达到尽量低。 3.1.2 应采取切实可行的方法，防止放射性污染扩散和材料的活 化。 3.1.3 应优先选用有毒有害成分少便于后续处理的材料，为废物 的最小化创造条件。对可复用的物料应提供再循环的技术手段。 3.1.4 应结合厂址核设施建设规划，以废物安全处理和处置为目 标，统筹考虑放射性废物处理和贮存设施，选择安全可靠的最小化 先进工艺技术和设备，制定本阶段废物最小化目标值。 3.1.5 应提出便于设施退役、实现退役废物最小化的技术措施。 3.1.6 核设施安全分析报告中应包括废物最小化相关内容。附件 Ⅰ给出了压水堆核电厂初步和最终安全分析报告中废物最小化相关内 容，其他核设施可参考。 3.1.7 核设施设计、建设单位及各级建造承包商应积极开展废物 最小化知识和技能培训，提高核设施设计、建造、安装及调试的质 量，为运行阶段设备安全运行及废物最小化奠定基础。 3.1.8 核设施设计单位应结合废物最小化技术发展及国内外运行 经验反馈，优化设计方案，推进废物最小化持续改进。 3.2 从源头减少放射性废物的产生 以下以压水堆核电厂为例，给出从源头减少放射性废物产生的 方法，其他核设施可供参考。 3.2.1 系统设计 3.2.1.1 通过采用长周期燃料循环、提高核电厂可用率（负荷因 子）等措施，减少放射性废物产生量。 3.2.1.2 通过优化设计（如用控制棒替代通过反应堆冷却剂硼浓 度变化调节反应性），减少反应堆冷却剂的上充和下泄，减少需后续 处理的废液量。 3.2.1.3 通过合理设置辐射分区、合理组织气流、物流方向、设 置放射性污染监测装置等措施，防止放射性污染扩散。 3.2.1.4 通过优化设计，合理确定设备、管道和阀门的数量。 3.2.1.5 提高盛装放射性物料系统的密封性能，减少放射性物质 的泄漏。 3.2.1.6 对于可能被放射性污染的混凝土和其他材质的表面采 用耐腐蚀、耐辐照涂层或钢覆面。 3.2.1.7 对于蒸汽发生器排污水、核岛通风系统凝结水及常规岛 液态流出物，需经收集后监测排放，若经分析放射性活度浓度超过 排放控制值，送往废液处理系统进行处理。 3.2.2 设备选择 3.2.2.1 采用高可靠性的燃料组件，改进燃料包壳性能，减少燃 料元件破损。 3.2.2.2 采用高可靠性、长寿命、便于维护和维修的设备，减少 设备泄漏及维修产生的废物。 3.2.2.3 采用先进的制造工艺（如对不锈钢表面进行酸洗钝化处 理，碳钢设备涂耐腐蚀涂层等），减少材料的腐蚀。 3.2.3 材料选择 3.2.3.1 与放射性介质接触的设备、管道和阀门，应采用适当的 不锈钢材料。严格限制与一回路反应堆冷却剂接触的设备、阀门、 管道和垫圈密封材料中钴、镍、银等元素的含量，主泵轴承材料中 锑的含量，以及堆腔辐射漏束中子可达区域部件和结构材料中钴、 镍等元素的含量，以减少活化腐蚀产物的产生。 3.2.3.2 与放射性介质接触的快速接头和阀门，应采用能够在特 定的介质环境条件下长期使用的密封材料，以降低腐蚀、泄漏和维 修频率。 3.2.3.3 在处理放射性液体的系统中，采用高交换容量的树脂， 以减少废树脂的产生量。 3.2.4 水化学控制 3.2.4.1 优化一回路水化学控制，如通过一回路加氢、注锌、停 堆前加双氧水等，采用有效的过滤、离子交换和膜技术的净化技术 等措施，提高一回路反应堆冷却剂水质，降低一回路设备的腐蚀和 侵蚀速率。 3.2.4.2 提高一回路补给水水质，减少进入堆芯活性区的杂质含 量。 3.3 放射性废物处理系统设计 以下以压水堆核电厂为例，为放射性废物处理系统设计环节开 展废物最小化提供指导，其他核设施可供参考。 3.3.1 工艺设计 3.1.1 应根据放射性废气的特性对其分类收集和处理。 3.3.1.2 当含氢放射性废气采用贮存衰变处理工艺时，根据废气 产生量（含大修工况）合理设置衰变箱个数和容积。 3.3.1.3 当含氢放射性废气采用活性炭延迟处理工艺时，合理确 定延迟床的台数和活性炭装量。应设置活性炭保护床或其他干燥措 施，避免活性炭因受潮而降低处理效率或过早失效。 3.3.1.4 根据放射性废液的物理、化学及放射性特性，分类收集 各类放射性废液，尤其要将含油废水、有机溶剂、含洗涤剂的洗衣 水和淋浴水与其他废液分开收集。 3.3.1.5 完善放射性废液相关系统的泄漏探测措施，及早发现和 排除泄漏。 3.3.1.6 根据各类废液的特性选择净化效率高、二次废物少的处 理工艺。 3.3.1.7 应严格评估和控制向核电厂各系统添加化学品的种类 和数量。 3.3.1.8 系统、设备、部件、器具、辐射防护用品、墙壁和地面 的清洗去污，应选择去污效率高、二次废物少的去污工艺和去污剂。 3.3.1.9 当采用离子交换除盐工艺处理可能含有胶体的工艺废液 时，宜对废液先进行预处理（如采用絮凝剂注入和深床过滤、超滤等 技术）。在离子交换除盐床前和最后一级离子交换除盐床后应设置过 滤器，以截留上游废水中的固体悬浮物及除盐床漏出的树脂碎屑。 3.3.1.10 为提高超滤、反渗透膜的寿命，在超滤、反渗透装置 前应设置预过滤装置。 3.3.1.11 内陆核电厂氚浓度较低废液，经处理后，水质若满足 复用要求，宜尽可能复用。 3.3.1.12 应采取措施，防止地下水、外部洪水、雨水或海水进 入厂房的控制区。 3.3.1.13 应注重在固体废物产生地对其分类收集，设置必要的 分拣装置并配备精度适用的辐射监测仪表，以便于对不同放射性活 度的废物进行分类，特别是将非放射性废物和被放射性核素轻微污 染经过贮存衰变后可清洁解控的废物从放射性废物中分拣出来，以 减少放射性废物产生量。 3.3.1.14 应结合本厂址或区域核电机组分布、废物源项和处置 场废物接收要求，统筹考虑放射性固体废物处理工艺，通过比选， 在成熟可靠的前提下，选择最佳可用的固体废物处理技术。常用的 放射性固体废物处理技术参见附录 B。 3.3.1.15 对于低放射性可燃废物的处理，宜优先采用焚烧等无 机化、稳定化处理技术；对于尺寸较大固体废物的处理，可先进行 必要的去污和剪切。 3.3.1.16 选用放射性废物的处理工艺时应确保形成的废物体和 废物包性能满足处置要求。 3.3.2 设备、阀门和管道的选型和设计 3.3.2.1 应根据物料的特性，选择质量可靠的设备、管道和阀门。 3.3.2.2 在设计文件中应对设备、管道和阀门内部的光洁度提出 要求，减少设备不规则内表面的数量，减少放射性腐蚀产物的沉积， 以便于进行去污，减少去污二次废物产生量。 3.3.2.3 除了泵、压缩机进出口、设备人孔、管道孔板等采用法 兰连接外，设备、管道和阀门应尽量采用焊接连接，并保证焊缝质 量，以减少潜在的泄漏。 3.3.2.4 应根据贮存介质的物理、化学和放射性特性，将设备溢 流水分别引入相应的收集槽或地坑，收集槽和地坑应设置液位报警 仪表和废液排出泵。 3.3.2.5 贮存放射性废液、浓缩液、废树脂、泥浆的贮槽应尽量 采用锥底或椭圆形底结构，以便能完全排空所装的物料。 3.3.2.6 放射性物料贮槽应设置液位（料位）测量仪表和报警装 置，防止发生溢出。 3.3.2.7 在满足贮存、运输和处置要求的前提下，应优先选用容 积利用率高、增容少的废物包装容器。 3.3.3 布置设计 3.3.3.1 在厂房和设备布置时，应考虑将装有较高放射性水平 物料的设备（如浓缩液贮槽、废树脂贮槽等）布置在专门的设备间 内，设备间宜根据实际情况设置钢托盘或钢覆面，钢托盘或钢覆面 的高度应足够容纳设备泄漏溢出的液体量，使物料泄漏时的污染限 制在最小范围内。设备间内应设置收集泄漏液体的地漏、排水沟或 地坑，地面应坡向地漏或地坑。 3.3.3.2 应设置必要的吊装和转运设备及运输通道，以利于将 污染区的设备或部件拆卸、转运到维修区进行维修。 3.3.3.3 盛装和输运放射性介质（如废树脂、放射性废液等） 的设备和管道应配置相应的疏水和排气点，输送管道应尽可能短， 并有适当的坡度和弯曲半径，以减少物料和放射性核素的沉积。 3.3.3.4 室内输送放射性液体的管道穿墙或楼板时宜设置套 管，应尽量避免将工艺管道直埋在混凝土结构内。 3.3.3.5 室外输送放射性废液的管道宜布置在管沟内或设置双 套管，并应考虑相应的泄漏监测手段，避免直埋地下。 4 运行阶段废物最小化 4.1 一般要求 4.1.1 核设施营运单位应根据国家相关法规的要求以及本厂的 实际情况，明确本厂废物最小化的组织机构和职责，充分发挥该机 构的策划、组织、协调、实施和监督作用，制订废物最小化目标和 改进计划，解决和处理核设施放射性废物管理的相关问题。 4.1.2 应将废物最小化纳入核设施的质量保证体系，编制并严格 执行放射性废物管理大纲和管理程序。 4.1.3 建立完善的放射性废物管理信息系统，做好放射性废物信 息的管理。 4.1.4 加强废物最小化知识和技能培训，使核设施所有员工（包 括承包商员工）都能够熟悉废物最小化的要求和目标，并在本部门 或个人的工作实践中贯彻落实。 4.1.5 应按时提交核设施运行年报中废物最小化的相关内容。附 件Ⅱ给出了压水堆核电厂运行年报中废物最小化内容，其他核设施可 供参考。 4.1.6 应及时总结废物最小化的管理经验，学习和借鉴国内外废 物最小化的良好实践，改进相关工作。我国核电厂废物最小化的良 好实践参见附录 C。 4.1.7 应重视风险分析和评估，针对废物处理系统可能发生的运 行事件（事故），制定相应的应急预案，做好应急准备，预防和减少 事件（事故）的发生，减轻事件（事故）对废物产生量的影响。 4.1.8 通过分类收集、贮存衰变、清洁解控、再循环/再利用等 运行管理措施减少放射性废物产生量。 4.1.9 应及时将废物包送往处置场处置，以减少暂存废物包锈 蚀、开裂导致放射性核素包容性下降的风险。 4.2 废物最小化管理措施 4.2.1 在核设施运行阶段应制定切实可行的废物管理计划，积极 推进废物最小化，加强核设施污染控制区的管理，防止污染扩散， 做好废物的测量、分类收集和处理。 4.2.2 加强日常运行计划、大修计划管理和设备管理，通过预防 性维修和纠正性维修等有效的维修策略以及工艺改进和设备升级来 提高设备的可靠性，确保废物管理相关系统安全运行。 4.2.3 减少和避免非计划停机、停堆；合理安排设备大修工序， 减少系统和设备的疏水次数，减少跑冒滴漏，减少废水产生量。 4.2.4 加强污染控制区防护用品和消耗材料管理，制定材料消耗 计划和控制指标，减少控制区维修和维护活动的材料消耗，从源头 减少放射性固体废物的产生。 4.2.5 采购耐用的个人防护用品，通过清洗、去污，多次重复使 用等措施，减少消耗量，减少放射性废物的产生。 4.2.6 及时清除废水收集罐、废水收集地坑的淤泥，以减少废液 处理系统滤芯的使用量。 4.2.7 采用钢制脚手架，减少木板用量；采用铝合金等金属工具 箱，便于去污，重复使用；对污染的工具采取去污，贮存衰变等措 施，减少报废量；放射性污染物品在厂内不同厂房之间的运输，宜 采用便于去污、经久耐用的金属箱或其他包装容器包装，减少包装 皮和塑料布的使用，防止污染扩散，减少废物产生。 4.2.8 综合考虑安全性、技术可行性、公众可接受性，并在代价 -利益分析的基础上，努力实现物料的再循环与再利用，如硼的回收 利用，废水、废酸、废碱等的再利用，劳动保护用品、污染的零部 件和工具清洗去污和修复后重复使用，污染的废钢铁去污后熔炼减 容、回收利用等。 4.2.9 编制废物管理统计报表，通过统计数据分析和查找管理上 的薄弱环节，持续改进，不断提高管理水平。 4.2.10 加强同国内外同行的技术交流，学习同行的管理经验。 4.3 废物最小化持续改进 4.3.1 核设施营运单位 每年应对废物最小化效果进行评价，并制定相应的改进措施。 4.3.2 运行核设施新建或改建废物处理设施应遵循本导则第 3 章的相关要求，统筹考虑全厂或区域放射性废物处理，选择最佳的 废物最小化先进工艺技术和设备。 4.3.3 对核设施放射性相关系统进行技术改进应遵循以下原则： （1）选择去污因子高、减容效果好、二次废物少且经过充分工 程验证的先进工艺和设备，并对二次废物进行有效处理； （2）应考虑原有厂房的布置空间、供电、通风、辅助介质的供 应等，选择最佳的时机进行技术改造，避免对设施的安全运行产生 影响； （3）应制订详细的改造方案和改造计划，在改造过程中落实废 物最小化和应急措施； （4）对于检修报废的设备、管道等部件，应尽可能地切割成易 于装入标准容器的小部件。对于难以切割减容的大型设备（如蒸汽 发生器、大尺寸热交换器等），应进行封闭和去除外表面污染，暂存 衰变，降低辐射水平后送处置场进行处置。