F75 放射性三废处理 标准查询与下载

EJ 914-2000 低、中水平放射性固体废物混凝土容器

本标准规定了低、.中水平放射性固体废物混凝土容器的规格.尺寸，制造技术要求和检验规则。 本标准适用于一切贮存，运输或处置低，中水平放射性固体废物的混凝土容器。

Concrete container for low-and intermediate-level radioactive solid wastes

ASTM C1220-98 放射性废物处置用整体废物形式静态浸出试验方法

1.1 This test method evaluates the relative chemical durability of simulated and radioactive monolithic waste forms such as glasses, ceramics, or cermets in various test solutions at temperatures lt;100176C under low surface-area-to-volume (S/V) ratio conditions. 1.2 This test method can be used to distinguish differences in the leaching behavior of various simulated or radioactive waste forms under the specific conditions of the test based on analysis of the test solution. Data from this test are used to calculate the normalized elemental mass loss from specimens exposed to aqueous solutions at temperatures lt;100176C. 1.3 Specimen surfaces may be altered during this test. These altered surfaces may be used to study the reaction of monolithic waste forms during static exposure to solutions. 1.4 This test method must be performed in accordance with all applicable quality assurance requirements for acceptance of the data. 1.5 This standard does not purport to address all of the safety problems, 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. For a specific hazard statement, see 7.3.2.

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

ASTM C1220-98(2004) 放射性废物处置用整体废物形式静态浸出试验方法

1.1 This test method covers the relative chemical durability of simulated and radioactive monolithic waste forms, such as glasses, ceramics, or cermets, in various test solutions at temperatures

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

EJ 1042-1996 低、中水平放射性固体废物包装容器.钢桶

Packaging container for low - and intermediate - level radioactive solid wastes steel drum

EJ/T 940-1995 核燃料后处理厂放射性废物管理技术规定

Technical Regulations on Radioactive Waste Management of Nuclear Fuel Reprocessing Plants

EJ/T 795-1993 低、中水平放射性废物减容系统技术规定

Technical regulations for low and medium level radioactive waste volume reduction system

ANSI/ANS 55.6-1993 轻水冷却反应堆中液体放射性废物的处理系统

This standard sets forth minimum design, construction, and performance requirements, with due consideration for operation, of the Liquid Radioactive Waste Processing System (LRWPS) for light water reactor (LWR) plants for design basis inputs. It is applicable to routine operation, including design basis fuel leakage and other design basis occurrences.

Liquid Radioactive Waste Processing Systems for Light Water Reactor Plants

ANSI/ANS 55.1-1992 轻水反应堆固体放射性废物的处理系统

This standard sets forth the design, construction, and performance requirements for a solid radioactive waste procesing system for light-water-cooled reactor plants. For the purposes of this standard, the solid radioactive waste processing system begins at the interface with the liquid radioactive waste processing system boundary and at the inlets to the spent resin, filter sludge, evaporator concentrate, and phase separator tanks. In addition, this standard pertains to dry active waste, mixed waste, and other solid radioactive waste forms that are generated as part of the operation and maintenance of light-water-cooled reactor plants. The system includes facilities for temporary (up to 30 days of anticipated normal waste generation) on-site storage of packaged waste but terminates at the point of loading the filled drums and other containers on a vehicle for shipping off-site to a licensed disposal site or transfer to interim (up to 5yr) on-site storage facilities. The solid radioactive waste processing system is not a safety-class system as defined by American National Standard Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, ANSI/ANS-51.1-1983(R1988) or as defined in American National Standard Nuclear Safety Criteria fo rthe Design of Stationary Boiling Water Reactor Plants, ANSI/ANS-52.1-1983(R1998).

Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants

EJ/T 532-1990 低、中水平放射性固体废物暂时贮存库安全分析报告要求

Requirements for Safety Analysis Report of Temporary Repository of Low- and Intermediate-level Radioactive Solid Waste

STAS 10148-1982 黑白电视显像管．一般质量技术要求

Monochrome television picture tubes. General technical requirements for quality

DIN 25455:1990 核电厂中放射性污染气体的处理.轻水反应堆

This standard is intended to apply to the systems of collection, conduct and treatment of radioactiv contaminated off-gas in nuclear power plants with preserised and boiling water reactors. The requirements are described to the systemtechnic design of the off-gas treatment systems, especially installations to evacuation, recombination and retention of gaseous radioactive materials (charcoal HEPA-filters).#,,#

Treatment of radioactive contaminated gases in nuclear power plants; light water reactors

ASTM C1144-89(2004) 易碎核废料模壳张裂强度试验方法

The splitting tensile-strength test can be used only on brittle waste materials such as ceramics, glass, concrete, or other materials that also have tensile fracture strengths that are less than one third of the compression strengths. The test cannot be used for metal-matrix, bituminous, plastic, or coated-particle waste forms. The strength values derived from this test cannot be applied to compressive-stress impact failure. The results apply only to tensile-stress failure. A separate compression-strength test, in which a cylindrical specimen is loaded on the flat surfaces, is required to determine compression strength along the lines of Test Methods C 39, D 2938, and C 773. Failures caused by impact must be determined in a separate test. This test method is applicable only to brittle solids because these are the only materials that fail under a definable stress state for the test specimen geometry and loading. For instance, extensive local shearing at or near the loading points that will also occur for plastically deformable solids, such as ductile metals or viscous polymers, will change the stress distribution sufficiently to invalidate the elastic-stress calculation used to obtain the tensile stress across the vertical fracture plane. Ductile materials will not, in many cases, fracture in the test. The effect of specimen size on the measured strength of brittle materials is not determined by this test method. In some materials, such as concretes, heterogeneities may be so large that tests on larger specimens are more representative. Testing along the lines of Test Method C 496 may then be appropriate to measure splitting tensile strength. This test method does not determine the effects of time and environment on strength, nor does it address failure under long-duration static loading. This test method can be used as a quality-control check and for optimizing waste form processing.1.1 This test method is used to measure the static splitting tensile strength of cylindrical specimens of brittle nuclear waste forms. It provides splitting tensile-strength data that can be used to compare the strength of waste forms when tests are done on one size of specimen.1.2 The test method is applicable to glass, ceramic, and concrete waste forms that are sufficiently homogeneous (Note 1) but not to coated-particle, metal-matrix, bituminous, or plastic waste forms, or concretes with large-scale heterogeneities. Cementitious waste forms with heterogeneities >1 to 2 mm and 5 mm can be tested using this procedure provided the specimen size is increased from the reference size of 12.7 mm diameter by 6 mm length, to 51 mm diameter by 100 mm length, as recommended in Test Method C 496 and Practice C 192. Note 18212;Generally, the specimen structural or microstructural heterogeneities must be less than about one-tenth the diameter of the specimen.1.3 This test method can be used as a quality control check on brittle waste forms and may be useful for optimizing waste form processing. Meaningful comparison of waste forms, however, requires data obtained on specimens of one size.1.4 The values stated in SI units are to be regarded as the standard.1.5 This standard may involve hazardous materials, operations, and equipment. 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. For specific hazard statements, see Section 7.

Standard Test Method for Splitting Tensile Strength for Brittle Nuclear Waste Forms

ASTM C1144-89(2011) 易碎核废料模壳张裂强度试验方法

The splitting tensile-strength test can be used only on brittle waste materials such as ceramics, glass, concrete, or other materials that also have tensile fracture strengths that are less than one third of the compression strengths.1.1 This test method is used to measure the static splitting tensile strength of cylindrical specimens of brittle nuclear waste forms. It provides splitting tensile-strength data that can be used to compare the strength of waste forms when tests are done on one size of specimen.1.2 The test method is applicable to glass, ceramic, and concrete waste forms that are sufficiently homogeneous (Note 1) but not to coated-particle, metal-matrix, bituminous, or plastic waste forms, or concretes with large-scale heterogeneities. Cementitious waste forms with heterogeneities >1 to 2 mm and 5 mm can be tested using this procedure provided the specimen size is increased from the reference size of 12.7 mm diameter by 6 mm length, to 51 mm diameter by 100 mm length, as recommended in Test Method C 496 and Practice C 192. Note 18212;Generally, the specimen structural or microstructural heterogeneities must be less than about one-tenth the diameter of the specimen.1.3 This test method can be used as a quality control check on brittle waste forms and may be useful for optimizing waste form processing. Meaningful comparison of waste forms, however, requires data obtained on specimens of one size.1.4 The values stated in SI units are to be regarded as the standard.1.5 This standard may involve hazardous materials, operations, and equipment. 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. For specific hazard statements, see Section 7.

Standard Test Method for Splitting Tensile Strength for Brittle Nuclear Waste Forms

ISO 6961:1982 凝固状放射性废物的长期沥滤试验

Long-term leach testing of solidified radioactive waste forms

ISO 6962:1982 高放射性废物固化体长期α辐照稳定性的标准试验方法

Standard method for testing the long term alpha irradiation stability of solidified high-level radioactive waste forms