F75 放射性三废处理 标准查询与下载

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

EJ 20059-2014 铀尾矿(渣)库安全技术规程

本标准规定了铀尾矿(渣)库安全管理的基本原则,铀尾矿(渣)库选址、设计、施工、生产运行、退役等全过程的安全技术方面的要求。本标准适用于铀水冶厂尾矿(渣)库。含有铀(钍)伴生矿的尾矿(渣)库亦可参照执行。

Safety technical criteria for uranium tailings pond

ISO 16966:2013 核能 核燃料技术 评估核反应堆产生的活性废物放射性的理论激活计算方法

This International Standard gives guidelines for a common basic theoretical methodology to evaluate the activity of radionuclides in activated waste generated at nuclear reactors using neutron activation calculations. The evaluation of any additional activity contributed by deposited contamination is not addressed in this International Standard.

Nuclear energy.Nuclear fuel technology.Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors

EJ/T 20012-2012 高放废物处置前管理技术规定

Technical regulations on pre-disposal management of high-level radioactive waste

EJ/T 20030-2012 低水平放射性可燃固体废物热解焚烧系统设计准则

Design criteria for low-level radioactive combustible solid waste pyrolysis incineration system

KS A ISO 6962:2012 核能.高放射性废物固化基质的长期α辐照稳定性的标准试验方法

이 표준은 조사된 시료에 대한 모든 특성 변화를 검출하여 알파 붕괴에 대한 고체의 장기간

Nuclear energy-Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioN waste

KS A ISO 14850-1:2012 核能.废弃物放射线的测定.第1部分:开放型结构统合模式高分解伽马光谱测定

KS A ISO 14850-1은 다음과 같은 방사능 분포가 균질한 폐기물 내 감마 방출 방

Nuclear energy-Waste-packages activity measurement-Part 1:High-resolution gamma spectrometry in integral mode with open geometry

NB/T 20106-2012 核电厂冷却水模拟技术规程

本标准规定了核电厂正常运行期间排放的冷却水和放射性液态流出物在受纳水体中稀释、扩散规律的模拟技术与方法。 本标准适用于核电厂选址和设计过程中冷却水和放射性液态流出物排放的数值模拟计算和物理模型试验。

Model regulation of cooling water for nuclear power plant

ASTM C992-11 核废料储存架用硼基中子吸收材料系统标准规格

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 ± 0.2 % 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 B10 areal density such that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool. 1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement. 1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.

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

ASTM C1220-10 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

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. The test is suitable for application to natural minerals, simulated waste form materials, and radioactive waste form material specimens. 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. This test method excludes the use of crushed or powdered specimens and organic materials. 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. 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. 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. 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. 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. 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). Note 18212;Additional requirements to the test method apply when using a highly radioactive waste form specimen, as indicated in the procedure.1.1 This test method provides a measure of the chemical durability of a simulated or radioactive monolithic waste form, such as a glass, ceramic, cement (grout), or cermet, in a test solution at temperatures <100°C under low specimen surface- area-to-leachant volume (S/V) ratio conditions. 1.2 This test method can be used to characterize the dissolution or leaching behaviors of various simulated or radioactive waste forms in various leachants under the specific conditions of the test based on analysis of the test solution. Data from this test are used to calculate normalized elemental mass loss values from specimens exposed to aqueous solutions at temperatures <100

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

DB11/ 639-2009 核技术利用放射性废物、废放射源收贮准则

本标准规定了北京市核技术利用过程中产生的放射性废物和废放射源的分类、处理、整备、包装、接收、运输、贮存、清洁解控和转移等环节的技术要求。本标准适用于北京市行政区域内核技术利用放射性废物的产生单位、运输单位以及城市放射性废物库管理单位对放射性废物和废放射源的管理。本标准不适用于核设施运行及其退役过程中产生的放射性废物和废放射源。

Guidelines for the storage and storage of radioactive waste and disused radioactive sources in the use of nuclear technology

ANSI/ANS 40.37-2009 可移动的低放射性废弃物处理系统

This standard sets forth design, fabrication, and performance recommendations and requirements for Mobile Low-Level Radioactive Waste Processing (MRWP) systems (including components) for nuclear facilities that generate Low Level Radioactive Wastes as defined by the Atomic Energy Act as amended. The purpose of this standard is to provide guidance to ensure that the MRWP systems are designed, fabricated, installed, and operated in a manner commensurate with the need to protect the health and safety of the public and plant personnel.

Mobile Low-Level Radioactive Waste Processing Systems

ANSI N14.33-2005 受损核废燃料的储存和运输

This standard defines terms related to dry storage and transport of damaged spent nuclear fuel. It establishes procedures for identifying, categorizing, and managing damaged fuel. The standard provides methods for identifying and classifying damaged spen

Storage and Transport of Damaged Spent Nuclear Fuel

ISO 6962:2004 核能.高放射性废物固化基质的长期α辐照稳定性的标准试验方法

This International Standard specifies a method designed to check the long-term stability of a solid to alpha disintegration by detection of all modifications in the properties of an irradiated sample. The material favoured hitherto is a borosilicate glass, but possible alternatives include: — ceramics or glass-ceramics, — other glass compositions.

Nuclear energy - Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioactive waste

ISO 14850-1:2004 核能.废弃物包装件的活性测量.第1部分:带公开几何条件的整体模型中的高分辨率γ光谱测定法

This part of ISO 14850 describes a procedure for measurements of gamma-emitting radionuclide activity in the following homogeneous objects: — unconditioned waste, including process waste (filters, control rods, etc.), dismantling waste, etc.; — waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 I, 200 I, 400 I or 800 I drums, and test specimens or samples, (vitrified waste); — waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.

Nuclear energy - Waste-packages activity measurement - Part 1: High-resolution gamma spectrometry in integral mode with open geometry

KS A ISO 6980:2003 校准剂量计和剂量强度计及测定充作为β辐射能量函数的灵敏度用的β标准放射源

이 규격은 베타 입자 에너지의 함수로서 방호용 선량계와 선량률계(1)의 교정 및 반응을

Reference beta radiations for calibrating dosimeters and dose-rate meters and for determining their response as a function of beta-radiation energy

ASTM C1207-03 无源中子复合计数法测定废弃物中钚的无损检验的标准试验方法

1.1 This test method describes the nondestructive assay of scrap or waste for plutonium content using passive thermal-neutron coincidence counting. This test method provides rapid results and can be applied to a variety of carefully sorted materials in containers as large as 208-L drums. The test method applies to measurements of 238Pu, 240Pu, and 242Pu and has been used to assay items whose total plutonium content ranges from 0.01 to 6000 g (1).1.2 This test method requires knowledge of the relative abundances of the plutonium isotopes to determine the total plutonium mass.1.3 This test method may not be applicable to the assay of scrap or waste containing other spontaneously fissioning nuclides.1.3.1 This test method may give biased results for measurements of containers that include large amounts of hydrogenous materials.1.3.2 The techniques described in this test method have been applied to materials other than scrap and waste (2, 3).1.4 This test method assumes the use of shift-register-based coincidence technology (4).1.5 Several other techniques that are related to passive neutron coincidence counting exist These include neutron multiplicity counting (5,6), add-a-source analysis (7), and cosmic-ray rejection (8). Discussions of these techniques are not included in this method.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 Test Method for Nondestructive Assay of Plutonium in Scrap and Waste by Passive Neutron Coincidence Counting

ASME AG-1-2003 核气体处理规范

Although this Code is written for nuclear power and nuclear fuel cycle facilities, the design requirements of these documents may be referenced for the design, fabrication, inspection, and testing of ventilation air cleaning and air conditioning equipment for other types of facilities. The user, however, is cautioned to carefully review these Code requirements for applicability to specific applications other than nuclear power and nuclear fuel cycle facilities. The user of the Code will note that metric equivalents of U.S. customary units appear throughout this issue of the Code. The values stated in U.S. customary units are to be regarded as the standard.

Code on Nuclear Air and Gas Treatment

EJ 1109.2-2002 低、中水平放射性废物近地表处置设施设计规定—岩洞型处置

本部分规定了低、 中水平放射性废物岩洞型近地表处罩设施的设计要求. 本部分适用于低、 中水平放射性废物岩洞型近地衰处置设施的设计.

Regulations for Design of Near Surface Disposal Facilities of Low and Intermediate Level Radioactive Wastes - Disposal in Rock Caverns

EJ 1109.1-2000 低、中水平放射性废物近地表处置设施设计规定—非岩洞型处置

本标准规定了低、中水平放射性废物非岩洞型近地表处置设施的设计规定和要求。 本标准适用于低、中水平放射性废物非岩洞型近地表处置设施的设计。

Regulations for design of near surface disposal facilities of low and Intermediate level radioactive wastes - disposal except in rock caverns