13.030.30 (Special wastes) 标准查询与下载

ASTM E1368-14 石棉消除项目外观检查的标准实施规程

5.1 This practice applies to response actions for all types of asbestos-containing materials, including surfacing materials, thermal systems insulation, and miscellaneous materials, whether friable or not, regardless of the quantities involved and the reason for conducting the response action. 5.1.1 Abatement for the purpose of removing asbestos-containing materials or encapsulating or enclosing them, regardless of the engineering controls and work practices used, requires performance of visual inspections as described in this practice. 5.1.2 Operations and maintenance (Oamp;M) activities, such as removal, encapsulation, or enclosure of asbestos-containing materials incidental to repair or replacement of a component, clean-up of debris from a fiber release episode, or other preventive measures, require the performance of visual inspections as described in this practice. See Managing Asbestos in Place and Guidance Manual. 5.1.3 This practice applies to response actions performed under a contract from the building owner, as well as to work performed by the building owner's staff. 5.2 The specific objectives of the visual inspection process before, during, and at the conclusion of an asbestos abatement project are: to review the extent of asbestos-containing material (ACM) within the scope of work, to monitor performance of the work, and to verify if visible residue, dust or debris, or unremoved material are absent at the completion of removal and clean-up activities. 5.2.1 The visual inspection process is used to evaluate all four aspects of an asbestos abatement project as follows: 5.2.1.1 Extent of ACM within Scope of Work—The building survey which is intended to locate and quantify asbestos-containing materials is not properly called a “visual inspection” within the context of this practice. To define the extent of ACM involved, a building survey is a necessary prelude to the first step of the visual inspection process. The building survey, which may use other building records, is intended to locate and assess the condition of ACM with confirmation by laboratory analysis of bulk samples. Additional surveys may be required during project design to find ACM in locations not entered or accessible during the initial building survey. The extent of the ACM to be abated must be known in order to properly design the abatement project. See 40 CFR Part 61. 5.2.1.2 Project Work Performance—Observation of work activities throughout the abatement project confirms acceptable work performance and aids the visual inspection for completeness of removal of ACM from the surfaces and components and for completeness of cleanup of the work area. Careful examination of the work area may be required at the start of the project for debris that may have been generated after the building surveys and project design. 5.2.1.3 Completeness of Abatement—The presence of residue, visible without the use of magnifying devices, on surfaces and components from which asbestos has been removed indicates that additional cleaning of these surfaces is required. All ACM required to be removed by the contract documents must be gone in order to pass the inspection for completeness of removal. Similarly, the presence of improperly encapsulated or insufficiently enclosed material indicates that these measures, if used for abatement or as an adjunct thereto, were inadequatel......

Standard Practice for Visual Inspection of Asbestos Abatement Projects

ASTM D5830-14 用气体色谱法进行危验废料溶剂分析的标准试验方法

4.1 This test method is useful in identifying the major solvent constituents in hazardous waste samples. This test method is designed to support field or site assessments, recycling operations, plant operations, or pollution control programs. 1.1 This test method is used to determine qualitatively and quantitatively the presence of the following compounds in waste samples using gas chromatography. This test method is designed for use as a screening method with a typical reporting level of 0.18201;%. Dichodifluoromethane Tetrahydrofuran Trichlorofluoromethane Acetone 1,1,2-Trichloro-1,2,2- 8199;trifluoroethane Methyl Ethyl Ketone MIBK Methanol Cyclohexanone Ethanol Ethyl Acetate Isopropanol Propyl Acetate n-Propanol Butyl Acetate Isobutanol Benzene n-Butanol Toluene tert-Butanol Ethylbenzene Methylene Chloride Xylenes Chloroform Styrene Carbon Tetrachloride Chlorobenzene 1,1-Dichloroethane Dichlorobenzenes 1,2-Dichloroethane

Standard Test Method for Solvents Analysis in Hazardous Waste Using Gas Chromatography

ASTM C1285-14 确定核废物和混合废弃玻璃及多相玻璃陶瓷耐化学性能的标准试验方法:产品一致性试验(PCT)

5.1 These test methods provide data useful for evaluating the chemical durability (see 3.1.5) of glass waste forms as measured by elemental release. Accordingly, it may be applicable throughout manufacturing, research, and development. 5.1.1 Test Method A can specifically be used to obtain data to evaluate whether the chemical durability of glass waste forms have been consistently controlled during production (see Table 1). 5.1.2 Test Method B can specifically be used to measure the chemical durability of glass waste forms under various test conditions, for example, varying test durations, test temperatures, ratios of sample-surface area (S) to leachant volume (V) (see Appendix X1), and leachant types (see Table 1). Data from this test may form part of the larger body of data that are necessary in the logical approach to long-term prediction of waste form behavior (see Practice C1174). 1.1 These product consistency test methods A and B provide a measure of the chemical durability of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, multiphase glass ceramic waste forms, or combinations thereof, hereafter collectively referred to as “glass waste forms” by measuring the concentrations of the chemical species released to a test solution under carefully controlled conditions. 1.1.1 Test Method A is a seven-day chemical durability test performed at 90 ± 2°C in a leachant of ASTM-Type I water. The test method is static and conducted in stainless steel vessels. The stainless steel vessels require a gasket to remain leak-tight.2 The stainless steel vessels are considered to be “closed system” tests. Test Method A can specifically be used to evaluate whether the chemical durability and elemental release characteristics of nuclear, hazardous, and mixed glass waste forms have been consistently controlled during production. This test method is applicable to radioactive and simulated glass waste forms as defined above. 1.1.2 Test Method B is a durability test that allows testing at various test durations, test temperatures, particle size and masses of glass sample, leachant volumes, and leachant compositions. This test method is static and can be conducted in stainless steel or PFA TFE-fluorocarbon vessels. The stainless steel vessels are considered to be “closed system” while the PFA TFE-fluorocarbon vessels are considered to be “open system” tests. Test Method B can specifically be used to evaluate the relative chemical durability characteristics of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, or multiphase glass ceramic waste forms, or combinations thereof. This test method is applicable to radioactive (nuclear) and mixed, hazardous, and simulated glass waste forms as defined above. Test Method B cannot be used as a consistency test for production of high level radioactive glass waste forms. 1.2 These test methods must be performed in accordance with all quality assurance requirements for acceptance of the data. 1.3 The values stated in SI units are to be regarded as standard. No other units of me......

Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test 40;PCT41;

ASTM C1463-13 化学和放射化学分析用含辐射和混合杂质溶解玻璃的标准操作规程

1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides. 1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements. 1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories. 1.4 Additional information relating to safety is included in the text. 1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass. 1.6 These practices are introduced to provide the user with an alternative means to Test Methods C169 for dissolution of waste containing glass in shielded facilities. Test Methods C169 is not practical for use in such facilities and with radioactive materials. 1.7 The ICP-AES methods in Test Methods C1109 and C1111 can be used to analyze the dissolved sample with additional sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can be found in Test Method C169. 1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance criteria. 1.9 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.10 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. Specific precautionary statements are given in Sections 10, 20, and 30.

Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis

ASTM D4447-10 实验室化学药品和样品的配置的标准指南

“Stand-alone” laboratories rarely generate or handle large volumes of hazardous substances. However, the safe handling and disposal of these substances is still a matter of concern. Since the promulgation of the Resource Conservation and Recovery Act (RCRA) of 1976, more attention has been given to the proper handling and disposal of such materials. States may adopt more stringent requirements; information on this may be found along the path EPA Home > Wastes > Regions/States/Tribes > RCRA State Authorization > Data, Charts and Graphs (STATS) > State/Regional. To keep track of this, EPA classifies state regulatory language as (1) authorized, (2) procedural/enforcement, (3) broader in scope, and (4) unauthorized, and it publishes notices concerning the first three in the Federal Register. Laboratory management should designate an individual who will be responsible for waste disposal and must review the RCRA guidelines, in particular: 40 CFR 261.3 - definition of a hazardous waste, 40 CFR 261.33 -specific substances listed as hazardous, 40 CFR 262 - generator requirements and exclusions, and proper shipping and manifesting procedures. Because many laboratory employees could be involved in the proper (and improper) treatment and disposal of laboratory chemicals and samples, it is suggested that a safety and training program be designed and presented to all regarding procedures to follow in the treatment and disposal of designated laboratory wastes and is required by the EPA (40 CFR 265.16). For those who pack and ship, Hazardous Materials Shipper training is also required by DOT (49 CFR 172.203). If practical and economically feasible, it is, of course, recommended that all laboratory waste be either recovered, re-used, or disposed of in-house. However, should this not be the case, other alternatives are presented. This guide is intended only as a suggested organized method for classification, segregation, and disposal of chemical laboratory waste. A university can set up its own chemical distributor to take orders from departments, order in economical quantities, sell at prorated bulk price plus expenses, and take back what is unused. For an example of a university central facility for minimizing over-ordering, storing chemical packages between uses, and disposing of hazardous wastes, see the web site of the University of Vermont, especially Procedure 12: Laboratory Waste Pickup and RCRA Hazardous Waste Determination. The handling of laboratory samples, especially those received in large numbers or quantities from a specific source, can often be accommodated by returning the material to the originator, so he can account or process them, or both, and potentially combine them with larger quantities for recycling or disposal. Shipments of hazardous waste, including samples, are subject to RCRA regulations that do not apply to shipments of what is similar but not waste-like. A sample that was not a waste as received, and has not been contaminated or labeled as waste, need not be a waste when it is returned. The small quantity generator exclusion (40 CFR 261.5) applies to some laboratories (those which generate less than 100 kg per month ~25 gal liquid). It is important to note that not every state allows the small quantity exclusion in this amount. Even so, the professional laboratory supervisor and his or her employers must balance the importance of (1) protecting human health and the environment from the adverse impact of potential mismanagement of small quantities of hazardous waste with (2) the need to hold the administrative and economic burden of management of these wastes under RCRA within reasonable an........

Standard Guide for Disposal of Laboratory Chemicals and Samples

ASTM C1109-10(2015) 使用电感耦合等离子-原子发射光谱法对核废料中浸出液分析试验方法

5.1 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 18201;% total solids. 5.2 This practice as written is for the analysis of solutions containing 18201;% (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 18201;% 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. 5.3 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 18201;% 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 Spectroscopy

ASTM D6050-09 有机液体有害废物中不溶固体测定的标准试验方法

A high percentage of insoluble, suspended solid material can create pumping, filtering, or grinding difficulties in the off-loading of bulk shipments of OLHW and can contribute to excessive wear on processing equipment. High solids can also decrease the quality and consistency of commingled solutions by decreasing the effectiveness of agitation in storage tanks. These issues are of concern to the recycling industries (solvents, paints, and other materials handled in significant quantities) in addition to those activities that propose to use the waste as a fuel.1.1 This test method covers the determination of the approximate amount of insoluble, suspended solid material in organic liquid hazardous waste (OLHW). 1.2 This test method is intended to be used in approximating the amount of insoluble, suspended solids in determining the material handling characteristics and fuel quality of OLHW. It is not intended to replace more sophisticated procedures for the determination of total solids. 1.3 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 Determination of Insoluble Solids in Organic Liquid Hazardous Waste

ASTM D6232-08 废弃物和污染介质数据收集活动用取样设备选择的标准指南

Although many technical papers address topics important to efficient and accurate sampling investigations (DQO''s, study design, QA/QC, data assessment; see Guides D 4687, D 5730, D 6009, D 6051, and Practice D 5283), the selection and use of appropriate sampling equipment is assumed or omitted. The choice of sampling equipment can be crucial to the task of collecting a sample appropriate for the intended use. When a sample is collected, all sources of potential bias should be considered, not only in the selection and use of the sampling device, but also in the interpretation and use of the data generated. Some major considerations in the selection of sampling equipment for the collection of a sample are listed below. The ability to access and extract from every relevant location in the target population, The ability to collect a sufficient mass of sample such that the distribution of particle sizes in the population are represented, and The ability to collect a sample without the addition or loss of constituents of interest. The characteristics discussed in 5.3 are particularly important in investigations when the target population is heterogeneous such as when particle sizes vary, liquids are present in distinct phases, a gaseous phase exists or material from different sources are present in the population. The consideration of these characteristics during the equipment selection process will enable the data user to make appropriate statistical inferences about the target population based on the sampling results.1.1 This guide covers criteria which should be considered when selecting sampling equipment for collecting environmental and waste samples for waste management activities. This guide includes a list of equipment that is used and is readily available. Many specialized sampling devices are not specifically included in this guide. However, the factors that should be weighed when choosing any piece of equipment are covered and remain the same for the selection of any piece of equipment. Sampling equipment described in this guide includes automatic samplers, pumps, bailers, tubes, scoops, spoons, shovels, dredges, coring and augering devices. The selection of sampling locations is outside the scope of this guide. 1.1.1 Table 1 lists selected equipment and its applicability to sampling matrices, including water (surface and ground), sediments, soils, liquids, multi-layered liquids, mixed solid-liquid phases, and consolidated and unconsolidated solids. The guide does not address specifically the collection of samples of any suspended materials from flowing rivers or streams. Refer to Guide D 4411 for more information. 1.2 Table 2 presents the same list of equipment and its applicability for use based on compatibility of sample and equipment; volume of the sample required; physical requirements such as power, size, and weight; ease of operation and decontamination; and whether it is reusable or disposable. 1.3 Table 3 provides the basis for selection of suitable equipment by the use of an Index. 1.4 Lists of advantages and disadvantages of selected sampling devices and line drawings and narratives describing the operation of sampling devices are also provided. 1.5 The values stated in both inch-pound and SI units are to be regarded separately as the standard units. The values given in parentheses are for information only. 1.6 This guide offers an organized collection of information or a series of options and does not recommend a specific course of action. This document cannot replace education or experience and should be used in con junction with professional judgement. Not all aspects of this guide may be ap......

Standard Guide for Selection of Sampling Equipment for Waste and Contaminated Media Data Collection Activities

ASTM C1500-08 用无源中子重复计数法对钚进行无损测定的试验方法

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. Measurements made with this test method may be suitable for safeguards or waste characterization requirements such as: Nuclear materials accountability, Inventory verification (7), Confirmation of nuclear materials content (8), Resolution of shipper/receiver differences (9), Excess weapons materials inspections (10, 11), Safeguards termination on waste (12, 13), Determination of fissile equivalent content (14). 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). 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. 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). For certain materials such as small Pu, items of less than 1 g, some Pu-bearing waste, or very impure Pu process residues where the (α,n) reaction rate overwhelms the triples signal, multiplicity information may not be useful because of the poor counting statistics of the triple coincidences within practical counting times (12). For pure Pu metal, pure oxide, or other well-characterized materials, the additional multiplicity information is not needed, and conventional coincidence counting will provide better repeatability because the low counting statistics of the triple coincidences are not used. Conventional coincidence information can be obtained either by changing to coincidence analyzer mode, or analyzing the multiplicity data in coincidence mode. The mathematical analysis of neutron multiplicity data is based on several assumptions that are detailed in Annex A1. The mathematical model considered is a point in space, with assumptions that neutron detection efficiency, die-away time, and multiplication are constant across the entire item (16, 17). As the measurement deviates from these assumptions, the biases will increase. Bias in passive neutron multiplicity measurements is related to deviations from the “point model” such as variations in detection efficiency, matrix composition, or distribution of nuclear material in the item''s interior. Heterogeneity in the distribution of nuclear material, neutron moderators, and neutron absorbers may introduce biases that affect the accuracy of the results. Measurements made on items with homogeneous contents will be more accurate than those made on items with inhomogeneous contents.1.1 This test method describes the nondestructive assay of plutonium in forms such as metal, oxide, scrap, residue, or waste using passive neutron multiplicity counting. This test method p......

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

ASTM C1174-07(2013) 高放射性废弃物地质处置的工程屏障体系(EBS)用包括废弃物形状材料长期性能的预测用标准实施规程

5.1 This practice supports the development of materials behavior models that can be used to predict alterations in materials over the very long time periods pertinent to the operation of a high-level nuclear waste repository; periods of time much longer than can be tested directly. Under the very extended service periods relevant to geological disposal—much longer periods than those encountered in normal engineering practice—equilibrium or steady state conditions may be achieved and models for reaction kinetics may be replaced by models, if justified, describing equilibrium extents of alteration. This practice is intended for use for waste form materials and materials proposed for use in an EBS that is designed to contain radionuclides released from high-level nuclear waste forms as they degrade over tens of thousands of years and more. Various U.S. Government regulations pertinent to repository disposal in the United States are as follows: 5.1.1 Public Law 97–425, the Nuclear Waste Policy Act of 1982, provides for the deep geologic disposal of high-level radioactive waste through a system of multiple barriers. The radiation release limits are to be set by the U.S. Environmental Protection Agency (EPA) (40 CFR 191). Licensing of such disposal will be done by the U.S. Nuclear Regulatory Commission (NRC). 5.1.2 The analyses described in this Standard Guide can be used to support the demonstration of compliance of the EBS components and design to the applicable requirements of 10 CFR 60 (pertaining to any HLW repository in the U.S.) and 10 CFR 63 (pertaining to the planned HLW repository at Yucca Mountain, NV). 5.1.2.1  10 CFR 60.135 and 60.113 require that the waste form be a material that is solid, non-particulate, non-pyrophoric, and non-chemically reactive, and that the waste package contain no liquid, particulates, chemically reactive or combustible materials and that the materials/components of the EBS be designed to provide – assuming anticipated processes and events - substantially complete containment of the HLW for the NRC-designated regulatory period. 5.1.2.2 10 CFR 63.113 provides that the EBS be designedsuch that, working in combination with the natural barriers, the performance assessment of the EBS demonstrates conformance to the annual reasonably expected individual dose protection standard of 10 CFR 63.311 and the reasonably maximally exposed individual standard of 10 CFR 63.312 , and shall not exceed EPA dose limits for protection of groundwater of 10 CFR 63.331 during the NRC-designated regulatory compliance period after permanent closure. 5.1.3 The regulations of the U.S. Environmental Protection Agency (EPA) in Part 191 of Title 40 of the CFR provide that cumulative releases of radionuclides from the disposa......

Standard Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste

ASTM D4447-06 实验室化学药品和样品的处理的标准指南

1.1 This guide is intended to provide the chemical laboratory manager with guidelines for the disposal of small quantities of laboratory wastes safely and in an environmentally sound manner. This guide is applicable to laboratories that generate small quantities of chemical or toxic wastes. Generally, such tasks include, but are not limited to, analytical chemistry, process control, and research or life science laboratories. It would be impossible to address the disposal of all waste from all types of laboratories. This guide is intended to address the more common laboratory waste streams.1.2 This guide is intended to support compliance with environmental laws in the United States of America. Some of these laws provide for states to take over regulation of air quality or natural water quality with the approval of the Environmental Protection Agency (EPA). Other matters, such as laboratory waste tracking, disposal as household garbage and use of sewers, are handled at the state, local or provider level throughout the country. Examples of providers are air scrubber services, municipal sewer systems, municipal and private garbage services, and treatment, storage or disposal facilities (TSD). Go to the EPA home page, click Wastes > Regions/States/Tribes > States to get help locating state regulations. Unfortunately, it is not possible for any one source to provide all the information necessary for laboratories to comply with all regulations. To ensure compliance, the laboratory manager must communicate with regulators at all four levels.1.3 Though it would be convenient to cite each reference by its Universal Resource Locator (URL), this guide eschews that (because such references are too labile) with the exception of http://www.epa.gov and http://es.epa.gov for the United States Environmental Protection Agency, http://www.dot.gov or http://www.hazmat.dot.gov for the United States Department of Transportation, and http://thomas.loc.gov to follow pending federal legislation in the United States. Intra-site links suggested here are also subject to obsolescence. However, one can enter in the web site search box the title of the document cited to locate it.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 Disposal of Laboratory Chemicals and Samples

ASTM E1368-05e1 石棉消除项目外观检查的标准实施规程

1.1 This practice covers procedures for performing visual inspections of asbestos response actions to:1.1.1 Establish the extent of the required work before it begins;1.1.2 Determine the progress and quality of the work and evaluate the completeness of the response action; and1.1.3 Evaluate the cleanliness of the work area prior to final air testing for clearance (if performed), and subsequent to dismantling of critical barriers.1.2 This practice can be used on an abatement project, or for operations and maintenance (OM) work, performed by the building owner's staff. It can also be used in conjunction with contract documents between the building owner and other parties involved in an abatement project. Note 1Standard contract documents (such as AIA and EJCDC documents) define contractual relationships and responsibilities for projects within the construction industry. Asbestos abatement projects differ from traditional construction projects in the manner of their design and execution, as well as in the type and level of oversight required to substantiate their successful completion. Non-traditional responsibilities are given to the building owner, project designer, and abatement contractor by this practice. Furthermore, responsibilities related to project oversight, inspections, and approvals are placed upon an additional non-traditional representative of the building owner; the project monitor, as defined by this practice. All parties are cautioned that the subject authorities and corresponding responsibilities be understood, mutually agreed upon, and correspondingly addressed with appropriate modifications, if necessary, to the contract documents for a specific project.1.3 This practice provides the following information:1.3.1 The objectives of the visual inspection process;1.3.2 The responsibilities and qualifications of the individuals involved in the visual inspections;1.3.3 The schedule of visual inspection activities during an abatement project and OM work;1.3.4 The inspection procedures for the various types of abatement work and OM tasks; and1.3.5 The criteria for certifying work as complete on the basis of the visual inspections.1.4 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.1.5 Warning-Asbestos fibers are acknowledged carcinogens. Breathing asbestos fibers can result in disease of the lungs including asbestosis, lung cancer, and mesothelioma. Precautions in this standard practice should be taken to avoid creating and breathing airborne asbestos particles from materials known or suspected to contain asbestos. See for regulatory requirements addressing asbestos.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 safety statements, see 12.2.

Standard Practice for Visual Inspection of Asbestos Abatement Projects

ASTM E1368-05 石棉消除项目外观检查的标准实施规程

1.1 This practice covers procedures for performing visual inspections of asbestos response actions to:1.1.1 Establish the extent of the required work before it begins;1.1.2 Determine the progress and quality of the work and evaluate the completeness of the response action; and1.1.3 Evaluate the cleanliness of the work area prior to final air testing for clearance (if performed), and subsequent to dismantling of critical barriers.1.2 This practice can be used on an abatement project, or for operations and maintenance (OM) work, performed by the building owner's staff. It can also be used in conjunction with contract documents between the building owner and other parties involved in an abatement project. Note 18212;Standard contract documents (such as AIA and EJCDC documents) define contractual relationships and responsibilities for projects within the construction industry. Asbestos abatement projects differ from traditional construction projects in the manner of their design and execution, as well as in the type and level of oversight required to substantiate their successful completion. Non-traditional responsibilities are given to the building owner, project designer, and abatement contractor by this practice. Furthermore, responsibilities related to project oversight, inspections, and approvals are placed upon an additional non-traditional representative of the building owner; the project monitor, as defined by this practice. All parties are cautioned that the subject authorities and corresponding responsibilities be understood, mutually agreed upon, and correspondingly addressed with appropriate modifications, if necessary, to the contract documents for a specific project.1.3 This practice provides the following information:1.3.1 The objectives of the visual inspection process;1.3.2 The responsibilities and qualifications of the individuals involved in the visual inspections;1.3.3 The schedule of visual inspection activities during an abatement project and OM work;1.3.4 The inspection procedures for the various types of abatement work and OM tasks; and1.3.5 The criteria for certifying work as complete on the basis of the visual inspections.1.4 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.1.5 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 safety statements, see 12.2.

Standard Practice for Visual Inspection of Asbestos Abatement Projects

ASTM C1109-04 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 C 1220. 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.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 The analysis must be conducted with an inductively coupled plasma-atomic emission spectrometer.1.5 The values stated in SI units are to be regarded as the standard.1.6 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

ASTM E1368-03 石棉消除项目外观检查的标准实施规范

1.1 This practice covers procedures for performing visual inspections of asbestos response actions to:1.1.1 Establish the extent of the required work before it begins;1.1.2 Determine the progress and quality of the work and evaluate the completeness of the response action; and1.1.3 Evaluate the cleanliness of the work area prior to final air testing for clearance (if performed), and subsequent to dismantling of critical barriers.1.2 This practice can be used on an abatement project, or for operations and maintenance (OM) work, performed by the building owner's staff. It can also be used in conjunction with contract documents between the building owner and other parties involved in an abatement project. Note 18212;Standard contract documents (such as AIA and EJCDC documents) define contractual relationships and responsibilities for projects within the construction industry. Asbestos abatement projects differ from traditional construction projects in the manner of their design and execution, as well as in the type and level of oversight required to substantiate their successful completion. Non-traditional responsibilities are given to the building owner, project designer, and abatement contractor by this practice. Furthermore, responsibilities related to project oversight, inspections, and approvals are placed upon an additional non-traditional representative of the building owner; the project monitor, as defined by this practice. All parties are cautioned that the subject authorities and corresponding responsibilities be understood, mutually agreed upon, and correspondingly addressed with appropriate modifications, if necessary, to the contract documents for a specific project.1.3 This practice provides the following information:1.3.1 The objectives of the visual inspection process;1.3.2 The responsibilities and qualifications of the individuals involved in the visual inspections;1.3.3 The schedule of visual inspection activities during an abatement project and OM work;1.3.4 The inspection procedures for the various types of abatement work and OM tasks; and1.3.5 The criteria for certifying work as complete on the basis of the visual inspections.1.4 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 safety statements, see 12.2.

Standard Practice for Visual Inspection of Asbestos Abatement Projects

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

ASTM C1571-03(2012) 热处理用放射性和/或危险废弃物表征的标准指南

This guide identifies methods to determine the physical and chemical characteristics of a variety of hazardous and/or radioactive wastes including heavy metal contaminated wastes. These wastes can be in the physical form of sludges (wet or dry), spent waste water filter aids, waste water filter cakes, incinerator ashes (wet or dry), incinerator blowdown (wet or dry), asbestos, resins, zeolites, soils, unset or unsatisfactory cementitious waste forms in need of remediation, lead paint wastes, radioactively or non-radioactively contaminated asbestos, geologic mill tailings (also known as byproduct materials) and other naturally occurring or accelerator produced radioactive materials (NORM and NARM), etc. and combinations of the above. This guide may not be applicable to piping, duct work, rubble, debris waste or wastes containing these components. This guide identifies the physical and chemical characteristics useful for developing high temperature thermal treatment methodologies for a variety of hazardous and/or radioactive process wastes and soils including heavy metal contaminated wastes. The waste characteristics can be used to (1) choose and develop the thermal treatment methodology, (2) determine if waste pretreatment is needed, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, and/or (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance. This guide identifies applicable test methods that can be used to measure the desired characteristics of the hazardous and/or radioactive wastes described in 4.1. The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be used to measure the amount and type of off-gas species present. However, this standard assumes that such sophisticated equipment is unavailable for radioactive or hazardous waste service due to potential contamination of the equipment. The analyses recommended are, therefore, the simplest and least costly analyses that can be performed and still considered adequate. Not every characteristic given in this guide is necessary for every waste (see Fig. 1). Cation analysis is necessary for every waste in order to determine whether the final waste form will be a homogeneous glass, a glass-ceramic, or a slag (see Appendix X1). Waste Analysis Method A is applicable when it is desired to know the amount and type of volatiles to be expected during thermal treatment and their compatibility with the thermal treatment and off-gas unit materials of construction and design capacity. These methods may be used to determine incinerator off-gas composition and concentrations. Waste analysis Method A is applicable when it is necessary to know the amount of organics in the waste independently of the amount of other volatile constituents present for safety concerns. These methods may be used to determine incinerator off-gas composition and concentrations. Waste analysis Method A is applicable when it is necessary to know if molten salt formation and accumulation in a thermal treatment unit in the presence of water vapor may be a safety concern. Waste Analysis Methods B and C are applicable when it is desired to only know the amount of volatiles to be expected during thermal treatment, for example, when speciation of the volatiles and potential molten salt formation is not of concern. These methods may be used to determi......

Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment

ASTM C1571-03 热处理用放射性和/或危险废弃物表征的标准指南

1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance. The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be used to measure the amount and type of off-gas species present. However, this standard assumes that such sophisticated equipment is unavailable for radioactive or hazardous waste service due to potential contamination of the equipment. The analyses recommended are, therefore, the simplest and least costly analyses that can be performed and still be considered adequate1.2 This guide is applicable to radioactive and/or hazardous wastes including but not limited to, high-level wastes, low-level wastes, transuranic (TRU) wastes, hazardous wastes, mixed (hazardous and radioactive) wastes, heavy metal contaminated wastes, and naturally occurring or accelerator produced radioactive material (NARM or NORM) wastes. These wastes can be in the physical form of wet sludges, dried sludges, spent waste water filter aids, waste water filter cakes, incinerator ashes (wet or dry), incinerator blowdown (wet or dry), wastewaters, asbestos, resins, zeolites, soils, unset or unsatisfactory cementitious wastes forms in need of remediation, lead paint wastes, etc. and combinations of the above. This guide may not be applicable to piping, duct work, rubble, debris waste or wastes containing these components.1.3 This guide references applicable test methods that can be used to characterize hazardous wastes, radioactive wastes, and heavy metal contaminated process wastes, waste forms, NARM or NORM wastes, and soils.1.4 These test methods must be performed in accordance with all quality assurance requirements for acceptance of the data.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.

Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment

ASTM D6232-03 废料和污染介质数据收集活动的抽样设备的选择的标准指南

1.1 This guide covers criteria that should be considered when selecting sampling equipment for collecting environmental and waste samples for waste management activities (see Guides D 4687, D 5730, D 6009, D 6051, and Practice D 5283). This guide includes a list of equipment that is used and is readily available. Many specialized sampling devices are not specifically included in this guide. However, the factors that should be weighed when choosing any piece of equipment are covered and remain the same for the selection of any piece of equipment. Sampling equipment described in this guide includes automatic samplers, pumps, bailers, tubes, scoops, spoons, shovels, dredges, coring and augering devices. The selection of sampling locations is outside the scope of this guide.1.1.1 Table 1 lists selected equipment and its applicability to sampling matrices, including water (surface and ground), sediments, soils, liquids, multi-layered liquids, mixed solid-liquid phases, and consolidated and unconsolidated solids. The guide does not address specifically the collection of samples of any suspended materials from flowing rivers or streams. Refer to Guide D 4411 for more information.1.2 Table 2 presents the same list of equipment and its applicability for use based on compatibility of sample and equipment; volume of the sample required; physical requirements such as power, size, and weight; ease of operation and decontamination; and whether it is reusable or disposable.1.3 Table 3 provides the basis for selection of suitable equipment by the use of an Index.1.4 Lists of advantages and disadvantages of selected sampling devices and line drawings and narratives describing the operation of sampling devices are also provided.1.5 The values stated in both inch-pound and SI units are to be regarded separately as the standard. The values given in parentheses are for information only.1.6 This guide offers an organized collection of information or a series of options and does not recommend a specific course of action. This guide cannot replace education or experience and should be used in conjunction with professional judgement. Not all aspects of this guide may be applicable in all circumstances. This guide is not intended to represent or replace the standard of care by which the adequacy of a given professional service must be judged, nor should this document be applied without consideration of a project''s many unique aspects. The word "Standard" in the title of this guide means only that it has been approved through the ASTM consensus process.1.7 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 Selection of Sampling Equipment for Waste and Contaminated Media Data Collection Activities

ASTM C1500-02 用无源中子重复计数法对钚进行无损分析的标准试验方法

1.1 This test method describes the nondestructive assay of plutonium in forms such as metal, oxide, scrap, residue, or waste using passive neutron multiplicity counting. This test method provides rapid results that are usually more accurate than conventional neutron coincidence counting. The method can be applied to a large variety of plutonium items in various geometries in cans, 208-L drums, or 1900-L Standard Waste Boxes. It has been used to assay items whose plutonium content ranges from 1 g to 1000's of g.1.2 There are several electronics or mathematical approaches available for multiplicity analysis, including the shift register, the Euratom Time Correlation Analyzer, and the List Mode Module, as described briefly in Ref. (1).1.3 This test method is primarily intended to address the assay of 240Pu-effective by moments-based multiplicity analysis using shift register electronics (1,2 ) and high efficiency neutron counters specifically designed for multiplicity analysis. This test method requires knowledge of the relative abundances of the plutonium isotopes to determine the total plutonium mass.1.4 This test method may also be applied to modified neutron coincidence counters which were not specifically designed as multiplicity counters, with a corresponding degradation of results.

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