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    ASTM C1571-2003 Standard Guide for Characterization of Radioactive and or Hazardous Wastes for Thermal Treatment《热处理用放射性和 或危险废弃物表征的标准指南》.pdf

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    ASTM C1571-2003 Standard Guide for Characterization of Radioactive and or Hazardous Wastes for Thermal Treatment《热处理用放射性和 或危险废弃物表征的标准指南》.pdf

    1、Designation: C 1571 03Standard Guide forCharacterization of Radioactive and/or Hazardous Wastesfor Thermal Treatment1This standard is issued under the fixed designation C 1571; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the ye

    2、ar of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 This guide identifies methods to determine the physicaland chemical characteristics of radioactive and/or hazar

    3、douswastes before a waste is processed at high temperatures, forexample, vitrification into a homogeneous glass ,glass-ceramic,or ceramic waste form. This includes waste forms produced byex-situ vitrification (ESV), in-situ vitrification (ISV), slagging,plasma-arc, hot-isostatic pressing (HIP) and/o

    4、r cold-pressingand sintering technologies. Note that this guide does notspecifically address high temperature waste treatment by in-cineration but several of the analyses described in this guidemay be useful diagnostic methods to determine incineratoroff-gas composition and concentrations.The charac

    5、terization of the waste(s) recommended in thisguide can be used to (1) choose and develop the appropriatethermal treatment methodology, (2) determine if waste pre-treatment is needed prior to thermal treatment, (3) aid indevelopment of thermal treatment process control, (4) developsurrogate waste fo

    6、rmulations, (5) perform treatability studies,(6) determine processing regions (envelopes) of acceptablewaste form composition, (7) perform pilot scale testing withactual or surrogate waste, and/or (8) determine the compositionand concentrations of off-gas species for regulatory compli-ance.The analy

    7、ses discussed in this standard can be performed bya 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-gasspecies present. However, this standard assumes that suchsophisticated equipment

    8、 is unavailable for radioactive or haz-ardous waste service due to potential contamination of theequipment. The analyses recommended are, therefore, thesimplest and least costly analyses that can be performed andstill be considered adequate1.2 This guide is applicable to radioactive and/or hazardous

    9、wastes including but not limited to, high-level wastes,2low-level wastes,3transuranic (TRU) wastes, hazardous wastes,mixed (hazardous and radioactive) wastes, heavy metal con-taminated wastes, and naturally occurring or accelerator pro-duced radioactive material (NARM or NORM) wastes. Thesewastes ca

    10、n be in the physical form of wet sludges, driedsludges, spent waste water filter aids, waste water filter cakes,incinerator ashes (wet or dry), incinerator blowdown (wet ordry), wastewaters, asbestos, resins, zeolites, soils, unset orunsatisfactory cementitious wastes forms in need of remedia-tion,

    11、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 canbe used to characterize hazardous wastes, radioactive wastes,and heavy meta

    12、l contaminated process wastes, waste forms,NARM or NORM wastes, and soils.1.4 These test methods must be performed in accordancewith all quality assurance requirements for acceptance of thedata.1.5 This standard may involve hazardous materials, opera-tions, and equipment. This standard does not purp

    13、ort toaddress all of the safety concerns, if any, associated with itsuse. It is the responsibility of the user of this standard toestablish appropriate safety and health practices and deter-mine the applicability of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:C 92 T

    14、est Methods for Sieve Analysis and Water Content ofRefractory Materials4C 146 Test Methods for Chemical Analysis of Glass Sand4C 162 Terminology of Glass and Glass Products41This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommitt

    15、ee C26.07 on Waste Materials.Current edition approved July 10, 2003. Published September 2003.2High level waste (HLW) is used as a generic term that includes high level liquidwaste (HLLW) and high level radioactive waste (HRW).3Low level waste (LLW) is used as a generic term that includes low level

    16、liquidwaste (LLLW), low level radioactive waste (LLRW) and low activity waste (LAW).4Annual Book of ASTM Standards, Vol 15.02.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.C 169 Methods for Chemical Analysis of Soda-Lime andBorosil

    17、icate Glass4C 242 Terminology of Ceramic Whitewares and RelatedProducts4C 859 Terminology Relating to Nuclear Materials5C 1109 Test Methods for Analysis of Aqueous Leachatesfrom Nuclear Waste Materials using Inductively CoupledPlasma-Atomic Emission Spectrometry5C 1111 Test Method for Determining El

    18、ements in WasteStreams by Inductively Coupled Plasma-Atomic EmissionSpectroscopy5C 1168 Practice for Preparation and Dissolution of Pluto-nium Materials for Analysis5C 1317 Practice for Dissolution of Silicate or Acid-Resistant Matrix Samples5C 1463 Practice for Dissolving Glass Containing Radioac-t

    19、ive and Mixed Waste for Chemical and RadiochemicalAnalysis5D 1129 Terminology Relating to Water6D 4327 Test Method for Anions in Water by Ion Chroma-tography62.2 Other Documents:US EPA Standard SW846, Test Methods for EvaluatingSolid WasteResource Conservation and Recovery Act (RCRA), 40CFR240-271,

    20、November 21, 1976DOE Methods for Evaluating Environmental and WasteManagement Samples, March, 1993, DOE.EM-0089T,Rev. 1Radioanalytical Technology for 10 CFR Part 61 and OtherSelected Radionuclides, Literature Review, C. W. Tho-mas, V. W. Thomas, and D. E. Robertson, PNNL-9444,March, 19963. Terminolo

    21、gy3.1 Definitions:3.1.1 analysis (physical or chemical)the determination ofphysical or chemical properties or composition of a material.C 8593.1.2 byproduct materialthe tailings or wastes producedby the extraction or concentration of uranium or thorium fromany ore processsed primarily for its source

    22、 material content,including discrete surface wastes, resulting from uraniumsolution extraction processes. Underground ore bodies de-pleted by such solution extraction operations do not constitute“byproduct material.” 10 CFR Part 40NOTE 1A supplementary definition can be found in 10 CFR Part 20;any r

    23、adioactive material (except special nuclear material) yielded in, ormade radioactive by, exposure to the process of producing or utilizingspecial nuclear material.3.1.3 calcineto fire or heat a granular or particulate solidat less than, fusion temperature but sufficient to remove most ofits chemical

    24、ly combined volatile matter (for example, H2O,CO2) and otherwise to develop the desired properties for use.73.1.4 debris wastesolid material exceeding a 60mm par-ticle size that is intended for disposal and that is: a manufac-tured object; or plant or animal matter; or natural geologicmaterial.83.1.

    25、5 devitrificationcrystallization of glass. C 1623.1.6 dryingremoval by evaporation, of uncombined wa-ter or other volatile substances from a ceramic raw material orproduct, usually expedited by low-temperature heating.C 2423.1.7 geologic mill tailingscommon rock leftover frommining or oil well drill

    26、ing operations that may contain hazard-ous or radioactive constituents, can include natural occurringradioactive material (NORM).3.1.8 glass ceramicsolid material, partly crystalline andpartly glass. C 1623.1.9 hazardous waste(a) in a broad sense, any substanceor mixture of substances having propert

    27、ies capable of produc-ing adverse effects on the health or safety of a human (see alsoRCRA hazardous waste); (b) any waste that is “listed” in40CFR Parts 261.31-261.33 or exhibits one or more of thecharacteristics identified in 40CFR Parts 261.20261.24, is amixture of hazardous and nonhazardous wast

    28、e, or is deter-mined to be hazardous waste by the generator.3.1.10 heavy metal contaminated wastea common haz-ardous waste; can damage organisms at low concentrations andtends to accumulate in the food chain. Examples are lead,chromium, cadmium, and mercury.3.1.11 high-level liquid waste (HLLW)the r

    29、adioactiveaqueous waste resulting from the operation of the first cycleextraction system, or equivalent concentrated wastes fromsubsequent extraction cycles, or equivalent wastes from aprocess not using solvent extraction, in a facility for processingirradiated reactor fuels.3.1.12 high-level radioa

    30、ctive waste (HLRW or HLW)(a)the highly radioactive material resulting from the reprocessingof spent nuclear fuel, including liquid waste produced directlyin reprocessing and any solid material derived from such liquidwaste that contains fission products (U.S. Code Title 42,Section 10101); (b) liquid

    31、 wastes resulting from the operationof the first cycle solvent extraction system, or equivalent, andthe concentrated wastes from subsequent extraction cycles, orequivalent, in a facility for reprocessing irradiated reactor fuel.3.1.13 homogeneous glass(1) an inorganic product offusion that has coole

    32、d to a rigid condition without crystallizing(see Terminology C 162); (2) a noncrystalline solid or anamorphous solid.93.1.14 incidental wastewastes that are not classified asHLW. NRC has defined three criteria that must be met for awaste to be called incidental waste: (1) wastes that have beenproces

    33、sed (or will be further processed) to remove key radio-nuclides to the maximum extent that is technically and eco-nomically practical; (2) wastes that will be incorporated in asolid physical form at a concentration that does not exceed theapplicable concentrations for Class C low-level waste; and (3

    34、)5Annual Book of ASTM Standards, Vol 12.01.6Annual Book of ASTM Standards, Vol 11.01.7Perkins, W. W., (Ed.), Ceramic Glossary, The American Ceramic Society, 1984.8Code of Federal Regulations Title 40, Volume 19, Part 268.9Varshneya, A. K., “Fundamentals of Inorganic Glasses,” Academic Press,Boston,

    35、MA, 1994.C1571032wastes that are to be managed pursuant of the Atomic EnergyAct, so that safety requirements comparable to the performanceobjectives set out in 10 CFR Part 61, Subpart C are satisfied.3.1.15 infrared incineratorany enclosed device that useselectric powered resistance heaters as a sou

    36、rce of radiant heatfollowed by an afterburner using controlled flame combustionand which is not listed as an industrial furnace EPA 40CFR 260.103.1.16 incineration(1) controlled flame combustion andneither meets the criteria for classification as a boiler, sludgedryer, or carbon regeneration unit, n

    37、or is listed as an industrialfurnace; or (2) meets the definition of infrared incinerator orplasma arc incinerator EPA 40 CFR 260.103.1.17 Joule heatingheating of glass by passing an elec-tric current through it, the powerful stirring effect of theconvection currents created by electric heating caus

    38、es unifor-mity of temperature throughout the body of glass and makes itphysically homogeneous.103.1.18 loss-on-heating (LOH)the percent loss in weightof a material at a constant temperature $105C , and for a timelong enough, to achieve constant weight, expressed as apercent of the initial weight of

    39、the dry material; The fractionalor percentage weight loss of a material on heating in air froman initial defined state (usually, dried) to a specified tempera-ture, such as 1000C, and holding there for a specified period,such as 1 hour. Fixed procedures are designed, usually, suchthat LOH represents

    40、 the loss of combined H2O, CO2, certainother volatile inorganics, and combustible organic matter.73.1.19 low-activity wastethe low-activity portion ofHLLW that is separated from the HLLW so that it can beclassified as LLW and be disposed of as “incidental waste.”3.1.20 low-level radioactive waste (L

    41、LRW or LLW)(a)LLRW is waste that satisfies the definition of LLRW in theRadioactive Waste Policy Amendments Act of 1985; radioac-tive material that is not high-level radioactive waste, spentnuclear fuel, or byproduct material as given in the AtomicEnergy Act of 1954; (b) Low level wastes are also no

    42、ttransuranic wastes as given in the Low Level RadioactiveWaste policy Amendments Act and 10 CFR Part 61; (c) wastethat (1) is not high-level radioactive waste, spent nuclear fuel,or byproduct material (as defined in section IIe(2) of theAtomic Energy Act of 1954, (42 U.S.C. 2014(e)(2); andwaste that

    43、 (2) the NRC, consistent with existing law and inaccordance with paragraph (a), classifies as low-level radioac-tive waste. Low-level radioactive waste (LLW) is a generalterm for a wide range of wastes. Industries, hospitals andmedical, educational, or research institutions; private or gov-ernment l

    44、aboratories; and nuclear fuel cycle facilities (forexample, nuclear power reactors and fuel fabrication plants)using radioactive materials generate low-level wastes as part oftheir normal operations. These wastes are generated in manyphysical and chemical forms and levels of contamination 10CFR Part

    45、 613.1.21 mixed wastewaste that contains both hazardouswaste and source special nuclear or byproduct material subjectto the Atomic Energy Act (AEA) of 1954;11The “radioactivecomponent” refers only to the actual radionuclides dispersed orsuspended in the waste substance.123.1.22 mixed waste glassa gl

    46、ass comprised of glass form-ing additives and hazardous waste that contains radioactiveconstituents.3.1.23 natural accelerator produced radioactive materials(NARM)radioactive materials not covered under the AtomicEnergy Act of 1954 that are naturally occurring or produced byan accelerator. Accelerat

    47、ors are used in sub-atomic particlephysics research. These materials have been traditionallyregulated by States. NARM waste with more than 2 nCi/g of226Ra or equivalent is commonly referred to as discrete NARMwaste; below this threshold, the waste is referred to as diffuseNARM waste. NARM waste is n

    48、ot covered under the AtomicEnergy Act, it is not a form of LLW, and it is not regulated byNuclear Regulatory Commission.3.1.24 naturally occurring radioactive materials(NORM)NORM refers to materials not covered under theAtomic Energy Act whose radioactivity has been enhanced(radionuclide concentrati

    49、ons are either increased or redistrib-uted where they are more likely to cause exposure to man)usually by mineral extraction or processing activities. Ex-amples are exploration and production wastes from the oil andnatural gas industry and phosphate slag piles from the phos-phate mining industry. This term is not used to describe ordiscuss the natural radioactivity of rocks and soils, or back-ground radiation, but instead refers to materials whose radio-activity is technologically enhanced by controllable practices.Note this definition is sometimes called tec


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