13.030.30 特殊废物 标准查询与下载

ASTM C1109-10 使用电感耦合等离子体原子发射光谱法分析核废料中浸出液的标准实施规程

This practice may be used to determine concentrations of elements leached from nuclear waste materials (glasses, ceramics, cements) using an aqueous leachant. If the nuclear waste material is radioactive, a suitably contained and shielded ICP-AES spectrometer system with a filtered exit-gas system must be used, but no other changes in the practice are required. The leachant may be deionized water or any aqueous solution containing less than 1 % total solids. This practice as written is for the analysis of solutions containing 1 % (v/v) nitric acid. It can be modified to specify the use of the same or another mineral acid at the same or higher concentration. In such cases, the only change needed in this practice is to substitute the preferred acid and concentration value whenever 1 % nitric acid appears here. It is important that the acid type and content of the reference and check solutions closely match the leachate solutions to be analyzed. This practice can be used to analyze leachates from static leach testing of waste forms using Test Method C1220. 1.1 This practice is applicable to the determination of low concentration and trace elements in aqueous leachate solutions produced by the leaching of nuclear waste materials, using inductively coupled plasma-atomic emission spectroscopy (ICP-AES). 1.2 The nuclear waste material may be a simulated (non-radioactive) solid waste form or an actual solid radioactive waste material. 1.3 The leachate may be deionized water or any natural or simulated leachate solution containing less than 1 % total dissolved solids. 1.4 This practice should be used by analysts experienced in the use of ICP-AES, the interpretation of spectral and non-spectral interferences, and procedures for their correction. 1.5 No detailed operating instructions are provided because of differences among various makes and models of suitable ICP-AES instruments. Instead, the analyst shall follow the instructions provided by the manufacturer of the particular instrument. This test method does not address comparative accuracy of different devices or the precision between instruments of the same make and model. 1.6 This practice contains notes that are explanatory and are not part of the mandatory requirements of the method. 1.7 The values stated in SI units are to be regarded as the standard. 1.8 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.

Standard Practice for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic Emission Spectrometry

ASME A112.14.6-2010 FOG(脂肪、油和油脂)处理系统

This document establishes requirements for FOG (fats, oils, and greases) disposal systems. FOG disposal systems shall be designed to (a) remove FOG from effluent (b) retain separated FOG (c) internally dispose retained FOG by means and methods of mass and volume reduction as required by para. 4.3.2 The use of alternate materials or methods are permitted, provided the proposed material and method complies with the performance requirements and intent of this Standard.

FOG (Fats, Oils, and Greases) Disposal Systems

ASTM C1207-10 无源中子符合计数法测定废弃物中钚的无损检验的标准试验方法

This test method is useful for determining the plutonium content of scrap and waste in containers ranging from small cans with volumes of the order of a mL to crates and boxes of several thousand liters in volume. A common application would be to 208-L (55-gal) drums. Total Pu content ranges from 10 mg to 6 kg (1). The upper limit may be restricted depending on specific matrix, calibration material, criticality safety, or counting equipment considerations. This test method is applicable for U.S. Department of Energy shipper/receiver confirmatory measurements (9), nuclear material diversion detection, and International Atomic Energy Agency attributes measurements (10). This test method should be used in conjunction with a scrap and waste management plan that segregates scrap and waste assay items into material categories according to some or all of the following criteria: bulk density, the chemical forms of the plutonium and the matrix, americium to plutonium isotopic ratio, and hydrogen content. Packaging for each category should be uniform with respect to size, shape, and composition of the container. Each material category might require calibration standards and may have different Pu mass limits. Bias in passive neutron coincidence measurements is related to item size and density, the homogeneity and composition of the matrix, and the quantity and distribution of the nuclear material. The precision of the measurement results is related to the quantity of nuclear material, the (α,n) reaction rate, and the count time of the measurement. For both benign matrix and matrix specific measurements, the method assumes the calibration reference materials match the items to be measured with respect to the homogeneity and composition of the matrix, the neutron moderator and absorber content, and the quantity of nuclear material, to the extent they affect the measurement. Measurements of smaller containers containing scrap and waste are generally more accurate than measurements of larger items. It is recommended that where feasible measurements be made on items with homogeneous contents. Heterogeneity in the distribution of nuclear material, neutron moderators, and neutron absorbers have the potential to cause biased results. The coincident neutron production rates measured by this test method are related to the mass of the even number isotopes of plutonium. If the relative abundances of these isotopes are not accurately known, biases in the total Pu assay value will result. Typical count times are in the range of 300 to 3600 s. Reliable results from the application of this method require training of the personnel who package the scrap and waste prior to measurement and of personnel who perform the measurements. Training guidance is available from ANSI 15.20, Guides , C1009, C1068, and C1490.1.1 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 several thousand liters in volume. The test method applies to measurements of 238Pu, 240Pu, and 242Pu and has been used to assay items whose total plutonium content ranges from 10 mg to 6 kg (1). 1.2 This test method requires knowledge of the rel......

Standard Test Method for Nondestructive Assay of Plutonium in Scrap and Waste by Passive Neutron Coincidence Counting

ANSI/ASME A112.14.6-2010 FOG(脂肪、油和润滑脂)处理系统

This Standard establishes requirements for FOG (Fats, Oils, and Greases) disposal systems. FOG disposal systems shall be designed to (a) remove FOG from effluent; (b) retain separated FOG; (c) internally dispose retained FOG by means and methods of mass and volume reduction as required by para. 4.3.2.; The use of alternate materials or methods are permitted, provided the proposed material and method complies with the performance requirements and intent of this Standard.

FOG (Fats, Oils, and Greases) Disposal Systems

ASTM D5608-10 用于低水平放射性废物场所的现场设备去污染标准规范

The primary objectives of work at low-level radioactive waste sites are the protection of personnel, prevention of the spread of contamination, minimization of additional wastes, protection of sample data quality, and the unconditional release of equipment used. Preventing the contamination of equipment used at low-level radioactive waste sites and the decontamination of contaminated equipment are key aspects of achieving these goals. This practice provides guidance in the planning of work to prevent contamination and when necessary, for the decontamination of equipment that has become contaminated. The benefits include: Minimizing the spread of contamination within a site and preventing the spread outside of the work area. Reducing the potential exposure of workers during the work and the subsequent decontamination of equipment. Minimizing the amounts of additional wastes generated during the work, including liquid, or mixed wastes, including separation of the waste types, such as protective clothing, cleaning equipment, cleaning solutions, and protective wraps and drapes. Improving the quality of sample data and reliability. This practice may not be applicable to all low-level radioactive waste sites, such as sites containing low-level radioactive wastes mixed with chemical or reactive wastes. Field personnel, with assistance from trained radiological control professionals, should have the flexibility to modify the decontamination procedures with due consideration for the sampling objectives, or if past experience supports alternative procedures for contamination protection or decontamination. This practice does not address the monitoring, protection, or decontamination of personnel working with low-level radioactive wastes. This practice does not address regulatory requirements that may control or restrict work, the need for permits or regulatory approvals, or the accumulation, handling, or disposal of generated wastes.1.1 These practices cover the decontamination of field equipment used in the sampling of soils, soil gas, sludges, surface water and ground water at waste sites known or suspected of containing low level radioactive wastes. 1.2 This practice is applicable at sites where low level radioactive wastes are known or suspected to exist. This practice may also be applicable for the decontamination of equipment used in known or suspected transuranic, or mixed wastes when used by itself or in conjunction with Practice D5088. 1.3 Procedures are contained in this practice for the decontamination of equipment that comes into contact with the sample matrix (sample contacting equipment), and for ancillary equipment that has not contacted the sample, but may have become contaminated during use (non-contacting equipment). For sample contacting equipment there are four separate procedures (Procedure A through D) in Section 8. For non-contacting equipment, one procedure is presented as covered in Section 9. 1.4 This practice is applicable to most conventional sampling equipment constructed of metallic and hard, smooth synthetic materials. Materials with rough or porous surfaces, or having a high sorption rate should not be used in radioactive waste sampling due to the difficulties with decontamination. 1.5 In those cases where sampling will be periodically performed, such as sampling of wells, consideration should be given to the use of dedicated sampling equipment if legitimate concerns exist for the production of undesirable or unmanageable waste byproducts, or both, during the decontamination of tools and equipment. 1.6 This practice does not address regulatory requirements for personnel protection or decontamination, or for the handling, labeling, s......

Standard Practices for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites

ASTM F1737/F1737M-10 溅溢响应过程中的溢油分散剂施用设备使用的标准指南:围油栏和管口系统

This guide provides information, procedures, and requirements for management and operation of dispersant spray application equipment (boom and nozzle systems) in oil spill response. This guide provides information on requirements for storage and maintenance of dispersant spray equipment and associated materials. This guide will aid operators in ensuring that a dispersant spray operation is carried out in an effective manner.1.1 This guide covers considerations for the maintenance, storage, and use of oil spill dispersant application systems. 1.2 This guide is applicable to spray systems employing booms and nozzles and not to other systems such as fire monitors or single-point spray systems. 1.3 This guide is applicable to systems employed on ships or boats and helicopters or airplanes. 1.4 This guide is one of five related to dispersant application systems. Guide F1413 covers design, Practice F1460 covers calibration, Test Method F1738 covers deposition, Guide F1737 covers the use of the systems, and Guide F2465 covers the design and specification for single-point spray systems. Familiarity with all five standards is recommended. 1.5 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard. 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 Guide for Use of Oil Spill Dispersant Application Equipment During Spill Response: Boom and Nozzle Systems

NF X30-500:2009 医疗保健废弃物的封装.穿孔废弃物用盒和小型收集器.试验和规范

Packaging for medicinal care waste - Boxes and small collectors for perforating waste - Specifications and tests.

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

DB50/T 271-2008 燃煤电厂脱硫石膏CaSO4.2H2O含量检测规定

本标准规定了燃煤电厂烟气脱硫石膏中CaSO4.2H2O的质量百分含量检测。本标准适用于重庆市辖区内燃煤发电厂采用湿式石灰/石灰石-石膏法烟气脱硫产生的脱硫石膏中所含CaSO4.2H2O质量百分百含量检测。

Coal-fired power plant desulfurization gypsum CaSO4.2H2O content detection regulations

CSA N292.3-2008(R2013) 低、中水平放射性废物的管理

1 Scope 1.1 This Standard specifies requirements for the management of low- and intermediate-level radioactive waste in solid, liquid, or gaseous states. 1.2 This Standard applies to organizations and facilities that generate, possess, manage, and transport lowand intermediate-level radioactive waste, including power reactors, research institutes, laboratories, and industrial facilities. 1.3 This Standard applies to facilities of all sizes (i.e., from storage cupboards to large purpose-built sites dedicated to the management of radioactive waste). 1.4 The following types of radioactive waste are not addressed in this Standard: (a) irradiated nuclear fuel; (b) naturally occurring radioactive material (NORM); (c) technologically enhanced, naturally occurring radioactive material (TENORM); (d) uranium mine and mill tailings; and (e) exempt waste (see Clause 3). 1.5 In CSA Standards, "shall" is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; "should" is used to express a recommendation or that which is advised but not required; "may" is used to express an option or that which is permissible within the limits of the standard; and "can" is used to express possibility or capability. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application.

Management of Low- and Intermediate-Level Radioactive Waste

ASTM C1500-08(2017) 用被动中子多重计数法无损测定钚的标准试验方法

5.1 This test method is useful for determining the plutonium content of items such as impure Pu oxide, mixed Pu/U oxide, oxidized Pu metal, Pu scrap and waste, Pu process residues, and weapons components. 5.2 Measurements made with this test method may be suitable for safeguards or waste characterization requirements such as: 5.2.1 Nuclear materials accountability, 5.2.2 Inventory verification (7), 5.2.3 Confirmation of nuclear materials content (8), 5.2.4 Resolution of shipper/receiver differences (9), 5.2.5 Excess weapons materials inspections (10, 11), 5.2.6 Safeguards termination on waste (12, 13), 5.2.7 Determination of fissile equivalent content (14). 5.3 A significant feature of neutron multiplicity counting is its ability to capture more information than neutron coincidence counting because of the availability of a third measured parameter, leading to reduced measurement bias for most material categories for which suitable precision can be attained. This feature also makes it possible to assay some in-plant materials that are not amenable to conventional coincidence counting, including moist or impure plutonium oxide, oxidized metal, and some categories of scrap, waste, and residues (10). 5.4 Calibration for many material types does not require representative standards. Thus, the technique can be used for inventory verification without calibration standards (7), although measurement bias may be lower if representative standards were available. 5.4.1 The repeatability of the measurement results due to counting statistics is related to the quantity of nuclear material, interfering neutrons, and the count time of the measurement (15) . 5.......

Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting

ASTM F1737-07 泄漏响应期间使用溢油分散剂应用设备的标准指南:喷枪和喷嘴系统

This guide provides information, procedures, and requirements for management and operation of dispersant spray application equipment (boom and nozzle systems) in oil spill response. This guide provides information on requirements for storage and maintenance of dispersant spray equipment and associated materials. This guide will aid operators in ensuring that a dispersant spray operation is carried out in an effective manner.1.1 This guide covers the essential considerations for the maintenance, storage, and use of oil spill dispersant application systems.1.2 This guide is applicable to spray systems employing booms and nozzles and not to other systems such as fire monitors, sonic distributors, or fan-spray guns.1.3 This guide is applicable to systems employed on ships or boats and helicopters or airplanes.1.4 This guide is one of four related to dispersant application systems. Guide F 1413 covers design, Practice F 1460 covers calibration, Test Method F 1738 covers deposition, and Guide F 1737 covers the use of the systems. Familiarity with all four standards is recommended.1.5 The values stated in SI units are to be regarded as the standard. The inch-pound units given in parentheses are for information only.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 Guide for Use of Oil Spill Dispersant Application Equipment During Spill Response: Boom and Nozzle Systems

ASME A112.14.6-2006 脂肪、油和油脂(FOG)的沉积系统

This Standard establishes requirements for FOG (Fats, Oils, and Greases) disposal systems. FOG disposal systems shall be designed to (a) remove FOG from effluent, (b) retain separated FOG, (c) internally dispose retained FOG by means and methods of mass and volume reduction as required by para 4.3.2. The use of alternate materials or methods are permitted, provided the proposed material and method complies with the performance requirements and intent of this Standard.

FOG (Fats, Oils, and Greases) Disposal Systems

EJ/T 1191-2005 推导退役后场址土壤中放射性残存物可接受活度浓度的照射情景、计算模式和参数

本标准规定了推导退役后场址土壤中放射性残存物可接受活度浓度的环境照射情景、照射途径、计算模式和主要参数。 本标准适用于退役后拟开放场址土壤中放射性残存物可接受活度浓度的确定。

Exposure scenarios, calculation models and parameters for driving acceptable levels of residual radioactive materials left in soil of a site following decommissioning

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

EJ/T 1190-2005 废镭源整备方法

本标准规定了废镭源整备的基本要求和事实程序。 本标准适用于废镭源的整备。

Method of spent radium source conditioning

CSA Z752-2003(C2013) 家庭危险废物的定义

1 Domaine d'application 1.1 Généralités Cette norme définit les déchets ménagers qui présentent des risques importants pour les humains ou l'environnement s'ils sont éliminés dans le flux des déchets ménagers ordinaires par l'intermédiaire d'un ou de plusieurs systèmes. Cette norme peut servir à: a) orienter le développement des produits ; b) élaborer des programmes de communication destinés à informer le public sur les matières qui répondent à la définition des DMD et sur la façon correcte de les éliminer ; c) faciliter et à encourager l'élaboration de programmes d'intendance des produits ; d) encadrer les activités de collecte et d'élimination des DMD. Cette norme est basée sur des pratiques, codes, normes, et règlements communément acceptés et utilisés au Canada. 1.2 Exclusions Cette norme ne s'applique pas intégralement dans certains cas où un système de gestion des déchets ne satisfait pas aux exigences minimales des normes ou règlements pertinents. Cette norme: a) ne présente pas de recommandations relatives à l'élimination, ni d'exigences spécifiques pour l'étiquetage en fonction des différentes catégories de déchets qu'elle décrit ; b) ne donne pas de conseils pour l'emballage des produits ménagers, ni pour leur utilisation ou entreposage à domicile ; c) ne traite pas des systèmes de gestion des déchets à l'extérieur du flux des déchets ménagers ordinaires (p. ex., les programmes d'intendance des produits de l'industrie et les programmes spéciaux de collecte des déchets ménagers) ; d) ne traite pas des dangers en milieu de travail associés à la gestion des matières par les programmes de DMD ; e) ne traite pas spécifiquement des cas d'élimination non autorisés ou illégaux de matières dangereuses (p. ex., dans les égouts pluviaux municipaux) ; f) ne traite pas des substances utilisées en milieu de travail.

Definition of household hazardous waste

NF X30-502:2003 医疗保健废物的封装.牙科用银汞合金废物封装.试验和规范

Packaging for medical care waste - Dental amalgam waste packaging - Tests and specifications.

ANSI/ANS 16.1-2003 用短期试验法测量已固化的低放射性废物的浸出性

This standard provides a uniform procedure to measure and index the release of radionuclides from waste forms as a result of leaching in demineralized water for five days (seven data points). The results cannot be interpreted to apply to any specific environmental situation except through correlative studies of actual disposal site conditions.

Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure

PD CEN/TR 14589:2003 废物料的特性.当前发展文件.固体基质中六价铬规范

This European document describes the state-of-the-art extraction and determination methods for the total content of hexavalent chromium in raw waste and other solid materials.

Characterization of waste State of the art document Chromium VI specification in solid matrices