ASTM C1682-2009 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Geologic Repository Disposal《核废料支援地学处置贮藏库的特性描述标准指南》.pdf

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1、Designation: C 1682 09Standard Guide forCharacterization of Spent Nuclear Fuel in Support ofGeologic Repository Disposal1This standard is issued under the fixed designation C 1682; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, th

2、e 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 be involved in characterizing the

3、 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 the individual tests/analyses may

4、 be usedas applicable to other spent fuels such as those from researchand test reactors. The testing is designed to provide informa-tion that supports the design, safety analysis, and performanceassessment of a geologic repository for the ultimate disposal ofthe SNF.1.2 The testing described include

5、s 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 as radionuclide con-tent, microstructure, and corrosion product co

6、ntent, and suchenvironmental response characteristics as drying rates, oxida-tion rates (in dry air, water vapor, and liquid water), ignitiontemperature, and dissolution/degradation rates. Not all of thecharacterization tests described herein must necessarily beperformed for any given analysis of SN

7、F repository perfor-mance, particularly in areas where an extensive body ofliterature already exists for the parameter of interest.1.3 It is assumed in formulating the SNF characterizationactivities in this guide that the SNF has been stored in aninterim storage facility at some time between reactor

8、 dischargeand dry transport to the geologic repository. The SNF may havebeen stored either wet (for example, a spent fuel pool), or dry(for example, an independent spent fuel storage installation(ISFSI), or both, and that the manner of interim storage mayaffect the SNF characteristics.1.4 The values

9、 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 of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safet

10、y and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2C 170/C 170M Test Method for Compressive Strength ofDimension StoneC 696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Gra

11、de Uranium Di-oxide Powders and PelletsC 698 Test Methods for Chemical, Mass Spectrometric, andSpectrochemicalAnalysis of Nuclear-Grade Mixed Oxides(U, Pu)O2)C 859 Terminology Relating to Nuclear MaterialsC 1174 Practice for Prediction of the Long-Term Behaviorof Materials, Including Waste Forms, Us

12、ed in EngineeredBarrier Systems (EBS) for Geological Disposal of High-Level Radioactive WasteC 1380 Test Method for the Determination of UraniumContent and Isotopic Composition by Isotope DilutionMass SpectrometryC 1413 Test Method for Isotopic Analysis of HydrolyzedUranium Hexafluoride and Uranyl N

13、itrate Solutions byThermal Ionization Mass SpectrometryC 1454 Guide for Pyrophoricity/Combustibility Testing inSupport of Pyrophoricity Analyses of Metallic UraniumSpent Nuclear FuelC 1553 Guide for Drying Behavior of Spent Nuclear FuelE 170 Terminology Relating to Radiation Measurementsand Dosimetr

14、y2.2 U.S. Government Documents3Code of Federal Regulations, Title 10, Part 60 Disposal of1This guide is under the jurisdiction 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 June 1, 2009. P

15、ublished July 2009.2For 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.3Available from U.S. Government Printing O

16、ffice Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.High-Level Radioactive Wastes in Geologic Repositories,U.S. Nucl

17、ear Regulatory Commission, January 1997Code of Federal Regulations, Title 10, Part 63 Disposal ofHigh-Level Radioactive Wastes in a Geologic Repositoryat Yucca Mountain, Nevada, U.S. Nuclear RegulatoryCommissionCode of Federal Regulations, Title 10, Part 71 Packagingand Transport of Radioactive Mate

18、rialsCode of Federal Regulations, Title 10, Part 72 LicensingRequirements for the Independent Storage of SpentNuclear Fuel and High-Level Radioactive WasteCode of Federal Regulations, Title 10, Part 961 Standardcontract for the Disposal of Spent Nuclear Fuel and/orHigh Level WasteCode of Federal Reg

19、ulations, Title 40, Part 191 Environ-mental Radiation Protection Standards for Managementand Disposal of Spent Nuclear Fuel, High-Level andTransuranic Radioactive WastesCode of Federal Regulations Title 40, Part 197 2005 Pro-tection of Environment: Public Health and EnvironmentalRadiation Standards

20、for Yucca Mountain, Nevada3. Terminology3.1 Definitions: Definitions used in this guide are as cur-rently existing in Terminology C 859 or Test Method C 170/C 170M, or as commonly accepted in dictionaries of theEnglish language, except for those terms defined below for thespecific usage of this stan

21、dard.3.2 Definitions of Terms Specific to This Standard:3.2.1 alteration, nany change 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

22、 materialsenvironment (for example, thermal conductivity, mechanicalproperties, radionuclide 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, electrocheimical polarization test

23、s,leach tests, solubility tests, etc).3.2.4 combustible, adjcapable of burning or 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

24、can be released from the fuel rod. (“The spent fuelcladding must be protected during 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

25、 storage,” Code of Federal Regulations, Title 10,Part 72, Section 122(h). It is not 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

26、of their irradiation or handling (orboth) have significantly altered dimensions or 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 crit

27、icality calculations (application dependentand function of the stage in the nuclear 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 fo

28、r in the evaluation of itsbehavior during transport, storage, or disposal (for example,cladding corrosion/thinning, hydride embrittlement, delayedhydride cracking, etc.).3.2.8 failed fuel (geologic disposal), nany significantalteration in the shape, dimensions, or configuration of a spentfuel assemb

29、ly or fuel element, or through-wall crack in thecladding, that could degrade or open further under long-termexposure 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

30、 can relocate or bereleased from the cladding.3.2.9.1 DiscussionCode of Federal Regulations, Title 40,Part 191, 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

31、 are based on the type of handlingnormal or specialrequired for transport and storage of theSNF. The “Standard” classification includes most normal andhandle-able LWR (PWR and BWR) spent fuel. “Non-Standard” spent fuel included non-LWR spent fuel, consoli-dated fuel, older design fuel, etc. “Failed”

32、 fuel includes: ClassF-1: (via visual examination) visual failure or damage“Assemblies which (i) are structurally deformed or havedamaged cladding to the extent that special handling may berequired or (ii) for any reason cant be handled with normalfuel handling equipment ” Class F-2: radioactive “ l

33、eakage”or “any fuel that allows gaseous communication between theinside and the outside of the cladding.” 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 40, Par

34、t191. Also, the Code of Federal Regulations, Title 40, Part 191categories of spent fuel are partially based on the fact that therepository is required 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, wh

35、ich is maintained without requiring an externalheat source.3.2.11 model, na simplified representation of a system orphenomenon, often mathematical.3.2.12 performance assessment (PA), nan analysis thatidentifies the processes and events that might affect thedisposal system; examines the effects of th

36、ese processes andevents on the performance of the disposal system; and,estimates the cumulative releases of radionuclides, consideringthe associated uncertainties, caused by all significant processesand events. These estimates shall be incorporated into anoverall probability distribution of cumulati

37、ve release to theC1682092extent practicable (see Code of Federal Regulations, Title 10,Part 63 Section 2) and Code of Federal Regulations, Title 40,Part 191 Section 15).3.2.13 pyrophoric, adjcapable of igniting spontaneouslyunder temperature, chemical, or physical/mechanical condi-tions specific to

38、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 their chemicaland physical properties.3.2.15 spent nuclear fuel (SNF), nnuclear fuel that hasbeen exposed to, and removed from, a nuclear rea

39、ctor.3.2.16 waste form (WF), n(from Practice C 1174) theradioactive waste materials and any encapsulating or stabiliz-ing matrix in which it is incorporated.3.2.17 waste package (WP), n(from Practice C 1174) thewaste form and any containers, shielding, packing and otherabsorbent materials immediatel

40、y surrounding an individualwaste container.4. Summary of Guide4.1 The characterization of spent nuclear fuel (SNF)insupport of interim dry storage, transport, and disposal in ageologic repositorydescribed in this guide includes theexamination/testing of such physical attributes as physicalappearance

41、, weight, density, shape/geometry, degree and typeof cladding damage, etc. It also includes the measurement/examination of such chemical aspects as drying characteristics,water content, radionuclide content, microstructure, zirconiumhydride content (of commercial SNF cladding), uranium hy-dride cont

42、ent (of metallic uranium SNF), and such environ-mental response characteristics as oxidation rate (in dry air,water vapor, and liquid water), ignition temperature, anddissolution/degradation rates.4.2 The primary issues involved in the characterization ofuranium dioxide-based commercial light water

43、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 of the fuel assembly (that is, the amountof “damaged fuel” as defined in Section 3 above), the amountand structure of zirconium hydride

44、 in the cladding (for ex-ample, “degraded cladding” as defined in Section 3 above),particularly with respect to high burnup LWR SNF. Also, theradionuclide content of the fuel, the thickness of the zirconiumoxide on the external surface of the cladding, and the leaching/dissolution behavior character

45、istics when in contact with the(repository-relevant) air/water environment are factors thatcould affect SNF behavior in repository disposal.4.3 The primary issue involved in characterization of me-tallic uranium SNF is the extent of damage to the cladding (thatis, exposure of metallic uranium to air

46、 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 unreproces

47、sed fuel. In some casesthe manner of discharge (for example, those involving physicaltrauma to the fuel element) of the fuel elements from thesereactors, and the type of wet storage environment in which theywere emplaced after discharge, has resulted in significantamounts of fuel cladding damage and

48、 extensive corrosion ofthe consequently exposed uranium metal. This corrosion anddamage has resulted in alteration of the physical integrity/dimensions of the elements and the chemical reactivity of thematerial such that the physical and chemical properties of thematerial no longer straightforwardly

49、 resemble, or can berepresented by, the properties of the as-fabricated, unirradiatedfuel.5. Significance and Use5.1 In order to demonstrate conformance to regulatoryrequirements and support the postclosure repository perfor-mance assessment information is required about the attributes,characteristics, and behavior of the SNF need to be determined.These properties of the SNF in turn support the transport,interim storage, and repository preclosure safety analyses, andrepository postclosure performance assessment. The interimdry storage of commercial LWR SN