F75 放射性三废处理 标准查询与下载

GB 41930-2022 低水平放射性废物包特性鉴定 水泥固化体

本标准规定了以水泥为主要固化（固定）介质的低水平放射性废物包特性鉴定要求和方法。 本标准适用于待近地表处置的低水平放射性废物包（包括固化体和固定体）的特性鉴定。 本标准不适用于使用高完整性容器的废物包的特性鉴定。

Characterization of low level radioactive waste packages—Cemented waste

GB 14569.1-2011 低、中水平放射性废物固化体性能要求－水泥固化体

本标准规定了低、中水平放射性废物固化体(以下简称水泥固化体)的最低性能要求和检验方法。 本标准适用于近地表处置的水泥固化体,大体积水泥浇注固化体除外。

Performance requirements for low and intermediate level radioactive waste form-Cemented waste form

GB 14500-2002 放射性废物管理规定

本标准规定了放射性废物的产生、收集、预处理、处理、整备、运输、贮存、处置与排放等各个阶段以及退役和环境整治等有关活动的管理目标和基本要求。 本标准适用于核燃料循环各环节和核技术应用与铀、钍伴生矿开发利用所产生的放射性废物的管理。其他实践所产生的放射性废物的管理亦可参照执行。

Regulations for radioactive waste management

GB 16933-1997 放射性废物近地表处置的废物接收准则

本标准规定了低、中水平放射性固体废物（以下简称“废物”）近地表处置时，废物接收的基本要求、接收准则和质量保证。 本标准适用于所有向上地表处置场发送的废物，其中主要是核电厂、核燃料循环和核设施退役所产生的废物。对放射性同位素生产和应用中所产生的废物也应参照执行。

Acceptance criteria for near surface disposal of radioactive waste

GB 14569.3-1995 低、中水平放射性废物固化体性能要求 沥青固化体

本标准规定了低、中水平放射性废物沥青固化体（以下简称沥青固化体）的最低性能要求和检验方法。 本标准适用于近地表处置的沥青固化体，岩洞处置的沥青固化体也可参照执行。

Characteristic requirements for solidified waste of low-and intermediate-level radioactive waste--Bitumen solidified waste

GB 14569.1-1993 低、中水平放射性废物固化体性能要求 水泥固化体

本标准规定了低、中水平放射性废物水泥固化体（以下简称水泥固化体）的最低性能要求和检验方法。 本标准适用于近地表处置的水泥固化体，岩洞处置的水泥固化体也可参照执行。

Characteristic requirements for solidified waste of low and intermediate level radioactive waste. Cement solidified waste

GB 14569.2-1993 低、中水平放射性废物固化体性能要求 塑料固化体

本标准规定了低、中水平放射性废物塑料固化体的最低性能要求和检验方法。 本标准适用于近地表处置的塑料固化体，岩洞处置的塑料固化体也可参照使用。

Characteristic requirements for solidified waste of low and intermediate level radioactive waste. Plastic solidified waste

GB 13600-1992 低中水平放射性固体废物的岩洞处置规定

本标准规定了低中水平放射性固体废物岩洞处置场的选址、设计、建造、运行、关闭和监督及其安全分析与环境影响评价的基本要求。 本标准适用于在废矿井、现有人工洞室、天然洞以及专门为处置废物而挖掘的岩洞中的废物处置。

Regulations for disposal of solid low-and intermediate level radioactive wastes in rock cavities

GB 11929-1989 高水平放射性废液贮存厂房设计规定

本标准规定了高水平放射性废液贮存厂房工艺设计所涉及的各方面的要求。 本标准适用于乏燃料后处理产生的高水平放射性废液及其浓缩液贮存厂房设计。对放射性浓度相当和含有多种长寿命放射性核素废液的贮存设施，在设计时也应参照使用。

Regulations for designing storage building of high level radioactive liquid waste

GB 11928-1989 低、中水平放射性固体废物暂时贮存规定

本标准规定了对低、中水平放射性固体废物暂时贮存的要求。 本标准适用于产生放射性固体废物的任何实践中，符合低、中水平的放射性固体废物的暂时贮存（以下简称“废物暂时贮存”）。 本规定不适用于尾矿渣类放射性固体废物的贮存管理。

Regulations for interim storage of low-and intermediate-level radioactive solid wastes

T/CIRA 4-2020 含14C生物废物管理规定

本标准规定了含14C生物废物安全管理的一般要求、特性鉴定、分类收集与包装、暂存、运输、预处理、处理、整备及处置等。 1.应根据GB5085（所有部分）和HJ298对废物进行危险废物特性鉴定； 2.含14C生物废物管理流程管理环节包含（特性鉴定、分类收集、暂存、运输、预处理、处理、整备、处置）

Regulations of 14C containing biological waste management

NB/T 20545-2019 核电厂放射性湿废物场内转运装置技术要求

Technical requirements for on-site transfer devices of radioactive wet waste in nuclear power plants

EJ/T 20159-2018 低、中水平放射性可压实固体废物超压处理接收准则

Acceptance criteria for overpressure treatment of low- and medium-level radioactive compactable solid waste

EJ/T 20156-2018 生产堆退役低、中放固体废物预处理要求

Requirements for pretreatment of low- and intermediate-level solid waste for decommissioning production reactors

EJ/T 20197-2018 低放可燃固体废物热解焚烧运行要求

Operation requirements for pyrolysis and incineration of low-level combustible solid waste

EJ/T 20157-2018 α废物处置前管理要求

αWaste pre-disposal management requirements

EJ/T 20158-2018 低、中水平放射性固体废物高压水射流去污要求

Requirements for decontamination of low- and medium-level radioactive solid waste by high-pressure water jetting

ASTM C1220-17 供进行放射性废物处理的整块废物的静力浸出的标准试验方法

5.1 This test method can be used to provide a measure of the reactivity of a material in a dilute solution in which the test response is dominated by the dissolution or leaching of the test specimen. It can be used to compare the dissolution or leaching behaviors of candidate radioactive waste forms and to study the reactions during static exposure to dilute solutions in which solution feed-back effects can be maintained negligible, depending on the test conditions. 5.2 The test is suitable for application to natural minerals, simulated waste form materials, and radioactive waste form material specimens. 5.3 Data from this test may form part of the larger body of data that is necessary in the logical approach to long-term prediction of waste form behavior, as described in Practice C1174. In particular, measured solution concentrations and characterizations of altered surfaces may be used in the validation of geochemical modeling codes. 5.4 This test method excludes the use of crushed or powdered specimens and organic materials. 5.5 Several reference test parameter values and reference leachant solutions are specified to facilitate the comparison of results of tests conducted with different materials and at different laboratories. However, other test parameter values and leachant solution compositions can be used to characterize the specimen reactivity. 5.5.1 Tests can be conducted with different leachant compositions to simulate groundwaters, buffer the leachate pH as the specimen dissolves, or measure the common ion effect of particular solutes. 5.5.2 Tests can be conducted to measure the effects of various test parameter values on the specimen response, including time, temperature, and S/V ratio. Tests conducted for different durations and at various temperatures provide insight into the reaction kinetics. Tests conducted at different S/V ratio provide insight into chemical affinity (solution feed-back effects) and the approach to saturation. 5.6 Either aerated or deaerated solutions may be used in this test method except when testing highly radioactive specimens. Deaerated solutions are mandatory in tests conducted with highly radioactive specimens to minimize the effects of nitrogen radiolysis. Preparation of deaerated leachants is addressed in 7.2.2. 5.7 Control of the oxygen fugacity is not part of this test method. Such control and measurement may be required for specific uses of test data but are beyond the scope of this test method. 5.8 Tests can be conducted using vessels compatible with the test specimen, leachant, and test environment. Corrosion resistant materials shall be used for tests with corrosive brines. Radiation-resistant materials shall be used for tests in radiation fields wherein the accumulated absorbed dose will exceed 104 rad (see Note 1).

Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste

ASTM C992-16 池环境中核燃料贮存架使用硼基中子吸收材料系统的标准规格

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system. 1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials. 1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.28201;% by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional – that is always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool. 1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a Pool Environment

EJ/T 20094-2014 铀矿冶建设项目竣工环境保护验收技术要求

本标准规定了铀矿冶建设项目梭工环境保护验收工作中建设单位验收资料准备、验收监测单位进行验收监测的技术程序及其技术要求。本标准适用于编制环境影响书的铀矿冶新建、改建、扩建建设项目竣工环境保护验收，对于编制环境影响报告表的建设项目竣工环境保可适当简化。

Technical requirements for environmental protection in uranium mining and metallurgy project for check and accept of completed project