ASTM C1682-17 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal.pdf

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1、Designation: C1682 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 oforiginal adopti

2、on 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 oftesting that would

3、 be involved in characterizing the physicaland chemical nature of spent nuclear fuel (SNF) in support ofits interim storage, transport, and disposal in a geologicrepository. This guide applies primarily to commercial lightwater reactor (LWR) spent fuel and spent fuel from weaponsproduction, although

4、 the individual tests/analyses may be usedas applicable to other spent fuels such as those from researchand test reactors and mixed oxide (MOX) spent fuel. Thetesting is designed to provide information that supports thedesign, safety analysis, and performance assessment of ageologic repository for t

5、he ultimate disposal of the SNF.1.2 The testing described includes characterization of suchphysical attributes as physical appearance, weight, density,shape/geometry, degree, and type of SNF cladding damage.The testing described also includes the measurement/examination of such chemical attributes a

6、s radionuclidecontent, microstructure, and corrosion product content, andsuch environmental response characteristics as drying rates,oxidation rates (in dry air, water vapor, and liquid water),ignition temperature, and dissolution/degradation rates. Not allof the characterization tests described her

7、ein must necessarilybe performed for any given analysis of SNF performance forinterim storage, transportation, or geological repositorydisposal, particularly in areas where an extensive body ofliterature already exists for the parameter of interest in thespecific service condition.1.3 It is assumed

8、in formulating the SNF characterizationactivities in this guide that the SNF has been stored in aninterim storage facility at some time between reactor dischargeand dry transport to a repository. The SNF may have beenstored either wet (for example, a spent fuel pool), or dry (forexample, an independ

9、ent spent fuel storage installation(ISFSI), or both, and that the manner of interim storage mayaffect the SNF characteristics.1.4 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.1.5 This standard does not purport to address all

10、of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.1.6 This international standard was developed in accor-dance with

11、 internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:

12、2C170/C170M Test Method for Compressive Strength ofDimension StoneC696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC698 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Mixe

13、d Ox-ides (U, Pu)O2)C859 Terminology Relating to Nuclear MaterialsC1174 Practice for Prediction of the Long-Term Behavior ofMaterials, Including Waste Forms, Used in EngineeredBarrier Systems (EBS) for Geological Disposal of High-Level Radioactive WasteC1380 Test Method for the Determination of Uran

14、ium Con-tent and Isotopic Composition by Isotope Dilution MassSpectrometryC1413 Test Method for Isotopic Analysis of HydrolyzedUranium Hexafluoride and Uranyl Nitrate Solutions byThermal Ionization Mass SpectrometryC1454 Guide for Pyrophoricity/Combustibility Testing in1This guide is under the juris

15、diction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel andHigh Level Waste.Current edition approved July 1, 2017. Published August 2017. Originallyapproved in 2009. Last previous edition approved in 2009 as C1682 09. DOI:10.1520/C1682

16、-17.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO B

17、ox C700, West Conshohocken, PA 19428-2959. United StatesThis international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recommendations issued by

18、the World Trade Organization Technical Barriers to Trade (TBT) Committee.1Support of Pyrophoricity Analyses of Metallic UraniumSpent Nuclear Fuel (Withdrawn 2016)3C1553 Guide for Drying Behavior of Spent Nuclear FuelE170 Terminology Relating to Radiation Measurements andDosimetry2.2 U.S. Government

19、Documents4Code of Federal Regulations, Title 10, Part 60 Disposal ofHigh-Level Radioactive Wastes in Geologic Repositories,U.S. Nuclear Regulatory CommissionCode of Federal Regulations, Title 10, Part 63 Disposal ofHigh-Level Radioactive Wastes in a Geologic Repositoryat Yucca Mountain, Nevada, U.S.

20、 Nuclear RegulatoryCommissionCode of Federal Regulations, Title 10, Part 71 Packagingand Transport of Radioactive MaterialsCode of Federal Regulations, Title 10, Part 72 LicensingRequirements for the Independent Storage of SpentNuclear Fuel and High-Level Radioactive WasteCode of Federal Regulations

21、, Title 10, Part 961 Standardcontract for the Disposal of Spent Nuclear Fuel and/orHigh Level WasteCode of Federal Regulations, Title 40, Part 191 Environmen-tal Radiation Protection Standards for Management andDisposal of Spent Nuclear Fuel, High-Level and Tran-suranic Radioactive WastesCode of Fed

22、eral Regulations Title 40, Part 197 Protection ofEnvironment: Public Health and Environmental RadiationStandards for Yucca Mountain, Nevada3. Terminology3.1 DefinitionsDefinitions used in this guide are as cur-rently existing in Terminology C859 or Test Method C170/C170M, or as commonly accepted in

23、dictionaries of theEnglish language, except for those terms defined below for thespecific usage of this standard. For consistency, many of thedefinitions are based on definitions from Federal Regulations inthe United States.3.2 Definitions of Terms Specific to This Standard:3.2.1 alteration, nany ch

24、ange to the form, state, or prop-erties of a material.3.2.2 attribute test, na test conducted to provide materialproperties that are required as input to materials behaviormodels, but are not themselves responses to the materialsenvironment (for example, thermal conductivity, mechanicalproperties, r

25、adionuclide content of waste forms, etc).3.2.3 characterization test, nany test conducted princi-pally to furnish information for a mechanistic understanding ofalteration (for example, electrochemical polarization tests,leach tests, solubility tests, etc).3.2.4 combustible, adjcapable of burning or

26、undergoingrapid 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 orpieces can be released from the fuel rod. (“The spent fuelcladding must be protected duri

27、ng storage against degradationthat leads to gross ruptures or the fuel must be otherwiseconfined such that degradation of the fuel during storage willnot pose operational safety problems with respect to itsremoval from storage,” Code of Federal Regulations, Title 10,Part 72, Section 122(h). It is no

28、t expected that minor claddingdefects such as pinhole cracks would permit significant releaseof particulate matter from the spent fuel rod.3.2.6 damaged fuel, nspent nuclear fuel elements orassemblies that as a result of their irradiation or handling (orboth) have significantly altered dimensions or

29、 claddingthrough-wall cracks or penetrations such that it cannot fulfill itsdirect or indirect regulatory or design function. For exampleany SNF assembly with rod(s) that are significantly displacedfor purposes of criticality calculations (application dependentand function of the stage in the nuclea

30、r fuel cycle).3.2.7 degraded cladding, nspent fuel cladding which hascorroded or been physically altered in-reactor or during sub-sequent interim storage (or both), to the extent that thealteration must be accounted for in the evaluation of itsbehavior during transport, storage, or disposal (for exa

31、mple,cladding corrosion/thinning, hydride embrittlement, etc.).3.2.8 failed fuel (geologic disposal), nany significantalteration in the shape, dimensions, or configuration of a spentfuel assembly or fuel element, or through-wall crack in thecladding, that could degrade or open further under long-ter

32、mexposure to the repository environment.3.2.9 failed fuel (interim storage and transport), nfuelrods/assemblies whose cladding has been perforated to theextent that powder or pieces of the fuel can relocate or bereleased from the cladding.3.2.9.1 DiscussionCode of Federal Regulations, Title 10,Part

33、961, the Standard Contract between the USDOE and theUS commercial nuclear utilities defines categories of commer-cial LWR spent fuel as “Standard,” “Non-Standard,” and“Failed.” These categories are based on the type of handlingnormal or specialrequired for transport and storage of theSNF. The “Stand

34、ard” classification includes most normal andhandle-able LWR (PWR and BWR) spent fuel. “Non-Standard” spent fuel includes non-LWR spent fuel, consoli-dated fuel, older design fuel, etc. “Failed” fuel includes: ClassF-1: (via visual examination) visual failure or damage“Assemblies which (i) are struct

35、urally deformed or havedamaged cladding to the extent that special handling may berequired or (ii) for any reason cannot be handled with normalfuel handling equipment” Class F-2: radioactive “ leakage”or “any fuel that allows gaseous communication between theinside and the outside of the cladding.”

36、Class F-3:EncapsulatedNote that the terms used in this guide for failedfuel, damaged fuel, and degraded cladding can fit the “FailedFuel” definition of Code of Federal Regulations, Title 10, Part961. Also, the Code of Federal Regulations, Title 10, Part 961categories of spent fuel are partially base

37、d on the fact that the3The last approved version of this historical standard is referenced onwww.astm.org.4Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.C1682 172repository is required

38、 by statute to accept all commercial LWRspent fuel, including damaged/failed.)3.2.10 ignite, vto cause to burn and reach a state of rapidoxidation, which is maintained without requiring an externalheat source.3.2.11 model, na simplified representation of a system orphenomenon, often mathematical.3.2

39、.12 performance assessment (PA), nan analysis thatidentifies the processes and events that might affect thedisposal system; examines the effects of these processes andevents on the performance of the disposal system; and,estimates the cumulative releases of radionuclides, consideringthe associated u

40、ncertainties, caused by all significant processesand events. These estimates shall be incorporated into anoverall probability distribution of cumulative release to theextent practicable (see Code of Federal Regulations, Title 10,Part 63 Section 2) and Code of Federal Regulations, Title 40,Part 191 S

41、ection 15).3.2.13 pyrophoric, adjcapable of igniting spontaneouslyunder temperature, chemical, or physical/mechanical condi-tions specific to the storage, handling, or transportation envi-ronment.3.2.14 sibling sample, none of two or more test samplesthat are nearly indistinguishable with respect to

42、 their chemicaland physical properties.3.2.15 spent nuclear fuel (SNF), nnuclear fuel that hasbeen exposed to, and removed from, a nuclear reactor.3.2.16 waste form (WF), n(from Practice C1174) theradioactive waste materials and any encapsulating or stabiliz-ing matrix in which it is incorporated.3.

43、2.17 waste package (WP), n(from Practice C1174) thewaste form and any containers, shielding, packing and otherabsorbent materials immediately surrounding an individualwaste container.4. Summary of Guide4.1 The characterization of spent nuclear fuel (SNF)insupport of interim storage, transport, and d

44、isposal 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 claddingdamage, etc. It also includes the measurement/examination ofsuch chemical aspects as drying character

45、istics, water content,radionuclide content, microstructure, zirconium hydride con-tent (of commercial SNF cladding), uranium hydride content(of metallic uranium SNF), and such environmental responsecharacteristics as oxidation rate (in dry air, water vapor, andliquid water), ignition temperature, an

46、d dissolution/degradation rates.4.2 The primary issues involved in the characterization ofuranium dioxide-based commercial light water reactor (LWR)SNF are the fraction of fuel rods with non-intact cladding (thatis, the amount of “failed fuel” as defined in Section 3 above),the structural integrity

47、of the fuel assembly (that is, the amountof “damaged fuel” as defined in Section 3 above), the amountand structure of zirconium hydride in the cladding (forexample, “degraded cladding” as defined in Section 3 above),particularly with respect to high burnup LWR SNF. Also, theradionuclide content of t

48、he fuel, the thickness of the zirconiumoxide on the external surface of the cladding, and the leaching/dissolution behavior characteristics when in contact with the(repository-relevant) air/water environment are factors thatcould affect SNF behavior in repository disposal.4.3 The primary issue invol

49、ved in characterization of me-tallic uranium SNF is the extent of damage to the cladding (thatis, exposure of metallic uranium to air and water) and itsconsequently enhanced chemical activity and pyrophoricity/combustibility characteristics. Metallic uranium SNF, largelyfrom plutonium production reactors, has been temporarilystored in water basins in several countries prior to reprocessingor ultimate direct disposal of unreprocessed fuel. In some casesthe manner of discharge (for example, those involving physicaltrauma to the fuel element) of the fuel