1、Designation: C1682 09C1682 17Standard Guide forCharacterization of Spent Nuclear Fuel in Support of InterimStorage, Transportation and Geologic Repository Disposal1This standard is issued under the fixed designation C1682; the number immediately following the designation indicates the year oforigina
2、l adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This guide provides guidance for the types and extent of testing t
3、hat would be involved in characterizing the physical andchemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. Thisguide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons producti
4、on, although theindividual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. reactors andmixed oxide (MOX) spent fuel. The testing is designed to provide information that supports the design, safety analysis, andperformance assessment of a g
5、eologic repository for the ultimate disposal of the SNF.1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density,shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination ofs
6、uch chemical attributes as radionuclide content, microstructure, and corrosion product content, and such environmental responsecharacteristics as drying rates, oxidation rates (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/degradation rates. Not all of the charact
7、erization tests described herein must necessarily be performed for any given analysis ofSNF repository performance,performance for interim storage, transportation, or geological repository disposal, particularly in areaswhere an extensive body of literature already exists for the parameter of intere
8、st.interest in the specific service condition.1.3 It is assumed in formulating the SNF characterization activities in this guide that the SNF has been stored in an interimstorage facility at some time between reactor discharge and dry transport to the geologic a repository. The SNF may have beenstor
9、ed either wet (for example, a spent fuel pool), or dry (for example, an independent spent fuel storage installation (ISFSI), orboth, and that the manner of interim storage may affect the SNF characteristics.1.4 The values stated in SI units are to be regarded as standard. No other units of measureme
10、nt are included in this standard.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatorylimitatio
11、ns prior to use.1.6 This international standard was developed in accordance with internationally recognized principles on standardizationestablished in the Decision on Principles for the Development of International Standards, Guides and Recommendations issuedby the World Trade Organization Technica
12、l Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:2C170/C170M Test Method for Compressive Strength of Dimension StoneC696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium DioxidePowders and PelletsC698 Test Methods for C
13、hemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides (U,Pu)O2)C859 Terminology Relating to Nuclear Materials1 This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
14、HighLevel Waste.Current edition approved June 1, 2009July 1, 2017. Published July 2009August 2017. Originally approved in 2009. Last previous edition approved in 2009 as C1682 09.DOI: 10.1520/C1682-09.10.1520/C1682-17.2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactAST
15、M Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the ASTM website.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made
16、 to the previous version. Becauseit may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyr
17、ight ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1C1174 Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered BarrierSystems (EBS) for Geological Disposal of High-Level Radioactive WasteC13
18、80 Test Method for the Determination of Uranium Content and Isotopic Composition by Isotope Dilution MassSpectrometryC1413 Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by ThermalIonization Mass SpectrometryC1454 Guide for Pyrophoricity/Combustibil
19、ity Testing in Support of PyrophoricityAnalyses of Metallic Uranium Spent NuclearFuel (Withdrawn 2016)3C1553 Guide for Drying Behavior of Spent Nuclear FuelE170 Terminology Relating to Radiation Measurements and Dosimetry2.2 U.S. Government Documents4Code of Federal Regulations, Title 10, Part 60 Di
20、sposal of High-Level Radioactive Wastes in Geologic Repositories, U.S.Nuclear Regulatory Commission, January 1997CommissionCode of Federal Regulations, Title 10, Part 63 Disposal of High-Level Radioactive Wastes in a Geologic Repository at YuccaMountain, Nevada, U.S. Nuclear Regulatory CommissionCod
21、e of Federal Regulations, Title 10, Part 71 Packaging and Transport of Radioactive MaterialsCode of Federal Regulations, Title 10, Part 72 Licensing Requirements for the Independent Storage of Spent Nuclear Fuel andHigh-Level Radioactive WasteCode of Federal Regulations, Title 10, Part 961 Standard
22、contract for the Disposal of Spent Nuclear Fuel and/or High LevelWasteCode of Federal Regulations, Title 40, Part 191 Environmental Radiation Protection Standards for Management and Disposalof Spent Nuclear Fuel, High-Level and Transuranic Radioactive WastesCode of Federal Regulations Title 40, Part
23、 197 2005 Protection of Environment: Public Health and Environmental RadiationStandards for Yucca Mountain, Nevada3. Terminology3.1 DefinitionsDefinitions used in this guide are as currently existing in Terminology C859 or Test Method C170/C170M, oras commonly accepted in dictionaries of the English
24、 language, except for those terms defined below for the specific usage of thisstandard. For consistency, many of the definitions are based on definitions from Federal Regulations in the United States.3.2 Definitions of Terms Specific to This Standard:3.2.1 alteration, nany change to the form, state,
25、 or properties of a material.3.2.2 attribute test, na test conducted to provide material properties that are required as input to materials behavior models,but are not themselves responses to the materials environment (for example, thermal conductivity, mechanical properties,radionuclide content of
26、waste forms, etc).3.2.3 characterization test, nany test conducted principally to furnish information for a mechanistic understanding ofalteration (for example, electrocheimicalelectrochemical polarization tests, leach tests, solubility tests, etc).3.2.4 combustible, adjcapable of burning or undergo
27、ing rapid chemical oxidation.3.2.5 breached fuel, n(per Code of Federal Regulations, Title 10, Part 72, Section 122(h) any spent fuel with extremedegradation or gross rupture, such that fuel particulates or pieces can be released from the fuel rod. (“The spent fuel cladding mustbe protected during s
28、torage against degradation that leads to gross ruptures or the fuel must be otherwise confined such thatdegradation of the fuel during storage will not pose operational safety problems with respect to its removal from storage,” Codeof Federal Regulations, Title 10, Part 72, Section 122(h). It is not
29、 expected that minor cladding defects such as pinhole crackswould permit significant release of particulate matter from the spent fuel rod.3.2.6 damaged fuel, nspent nuclear fuel elements or assemblies that as a result of their irradiation or handling (or both) havesignificantly altered dimensions o
30、r cladding through-wall cracks or penetrations such that it cannot fulfill its direct or indirectregulatory or design function. For example any SNF assembly with rod(s) that are significantly displaced for purposes of criticalitycalculations (application dependent and function of the stage in the nu
31、clear fuel cycle).3.2.7 degraded cladding, nspent fuel cladding which has corroded or been physically altered in-reactor or during subsequentinterim storage (or both), to the extent that the alteration must be accounted for in the evaluation of its behavior during transport,storage, or disposal (for
32、 example, cladding corrosion/thinning, hydride embrittlement, delayed hydride cracking, etc.).3.2.8 failed fuel (geologic disposal), nany significant alteration in the shape, dimensions, or configuration of a spent fuelassembly or fuel element, or through-wall crack in the cladding, that could degra
33、de or open further under long-term exposure tothe repository environment.3 The last approved version of this historical standard is referenced on www.astm.org.4 Available from U.S. Government Printing Office Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, h
34、ttp:/www.access.gpo.gov.C1682 1723.2.9 failed fuel (interim storage and transport), nfuel rods/assemblies whose cladding has been perforated to the extent thatpowder or pieces of the fuel can relocate or be released from the cladding.3.2.9.1 DiscussionCode of Federal Regulations,Title 40,10, Part 19
35、1,961, the Standard Contract between the USDOE and the US commercial nuclearutilities defines categories of commercial LWR spent fuel as “Standard,” “Non-Standard,” and “Failed.” These categories are basedon the type of handlingnormal or specialrequired for transport and storage of the SNF. The “Sta
36、ndard” classification includesmost normal and handle-able LWR (PWR and BWR) spent fuel. “Non-Standard” spent fuel includedincludes non-LWR spent fuel,consolidated fuel, older design fuel, etc. “Failed” fuel includes: Class F-1: (via visual examination) visual failure ordamage“Assemblies which (i) ar
37、e structurally deformed or have damaged cladding to the extent that special handling may berequired or (ii) for any reason cantcannot be handled with normal fuel handling equipment” Class F-2: radioactive “ leakage”or “any fuel that allows gaseous communication between the inside and the outside of
38、the cladding.” Class F-3: EncapsulatedNote that the terms used in this guide for failed fuel, damaged fuel, and degraded cladding can fit the “Failed Fuel” definition ofCode of Federal Regulations, Title 40,10, Part 191.961.Also, the Code of Federal Regulations, Title 40,10, Part 191961 categoriesof
39、 spent fuel are partially based on the fact that the repository is required by statute to accept all commercial LWR spent fuel,including damaged/failed.)3.2.10 ignite, vto cause to burn and reach a state of rapid oxidation, which is maintained without requiring an external heatsource.3.2.11 model, n
40、a simplified representation of a system or phenomenon, often mathematical.3.2.12 performance assessment (PA), nan analysis that identifies the processes and events that might affect the disposalsystem; examines the effects of these processes and events on the performance of the disposal system; and,
41、 estimates thecumulative releases of radionuclides, considering the associated uncertainties, caused by all significant processes and events. Theseestimates shall be incorporated into an overall probability distribution of cumulative release to the extent practicable (see Code ofFederal Regulations,
42、 Title 10, Part 63 Section 2) and Code of Federal Regulations, Title 40, Part 191 Section 15).3.2.13 pyrophoric, adjcapable of igniting spontaneously under temperature, chemical, or physical/mechanical conditionsspecific to the storage, handling, or transportation environment.3.2.14 sibling sample,
43、none of two or more test samples that are nearly indistinguishable with respect to their chemical andphysical properties.3.2.15 spent nuclear fuel (SNF), nnuclear fuel that has been exposed to, and removed from, a nuclear reactor.3.2.16 waste form (WF), n(from Practice C1174) the radioactive waste m
44、aterials and any encapsulating or stabilizing matrixin which it is incorporated.3.2.17 waste package (WP), n(from Practice C1174) the waste form and any containers, shielding, packing and otherabsorbent materials immediately surrounding an individual waste container.4. Summary of Guide4.1 The charac
45、terization of spent nuclear fuel (SNF)in support of interim dry storage, transport, and disposal in a geologicrepositorydescribed in this guide includes the examination/testing of such physical attributes as physical appearance, weight,density, shape/geometry, degree and type of cladding damage, etc
46、. It also includes the measurement/examination of such chemicalaspects as drying characteristics, water content, radionuclide content, microstructure, zirconium hydride content (of commercialSNF cladding), uranium hydride content (of metallic uranium SNF), and such environmental response characteris
47、tics as oxidationrate (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/degradation rates.4.2 The primary issues involved in the characterization of uranium dioxide-based commercial light water reactor (LWR) SNFare the fraction of fuel rods with non-intact cladding (
48、that is, the amount of “failed fuel” as defined in Section 3 above), thestructural integrity of the fuel assembly (that is, the amount of “damaged fuel” as defined in Section 3 above), the amount andstructure of zirconium hydride in the cladding (for example, “degraded cladding” as defined in Sectio
49、n 3 above), particularly withrespect to high burnup LWR SNF. Also, the radionuclide content of the fuel, the thickness of the zirconium oxide on the externalsurface of the cladding, and the leaching/dissolution behavior characteristics when in contact with the (repository-relevant)air/water environment are factors that could affect SNF behavior in repository disposal.4.3 The primary issue involved in characterization of metallic uranium SNF is the extent of damage to the cladding (that is,exposure of metallic uranium to air and water) and its conseq
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