1、Designation: C1431 99 (Reapproved 2018)Standard Guide forCorrosion Testing of Aluminum-Based Spent Nuclear Fuel inSupport of Repository Disposal1This standard is issued under the fixed designation C1431; the number immediately following the designation indicates the year oforiginal adoption or, in t
2、he 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 covers corrosion testing of aluminum-basedspent nuclear fuel in support of
3、 geologic repository disposal(per the requirements in 10 CFR 60 and 40CFR191). Thetesting described in this document is designed to provide datafor analysis of the chemical stability and radionuclide releasebehavior of aluminum-based waste forms produced fromaluminum-based spent nuclear fuels. The d
4、ata and analysesfrom the corrosion testing will support the technical basis forinclusion of aluminum-based spent nuclear fuels in the reposi-tory source term. Interim storage and transportation of thespent fuel will precede geologic disposal; therefore, referenceis also made to the requirements for
5、interim storage (per 10CFR 72) and transportation (per 10 CFR 71). The analyses thatwill be based on the data developed are also necessary tosupport the safety analyses reports (SARs) and performanceassessments (PAs) for disposal systems.1.2 Spent nuclear fuel that is not reprocessed must be safelym
6、anaged prior to transportation to, and disposal in, a geologicrepository. Placement in an interim storage facility may includedirect placement of the irradiated fuel or treatment of the fuelprior to placement, or both. The aluminum-based waste formsmay be required to be ready for geologic disposal,
7、or roadready, prior to placement in extended interim storage. Interimstorage facilities, in the United States, handle fuel from civiliancommercial power reactors, defense nuclear materials produc-tion reactors, and research reactors. The research reactorsinclude both foreign and domestic reactors. T
8、he aluminum-based fuels in the spent fuel inventory in the United States areprimarily from defense reactors and from foreign and domesticresearch reactors. The aluminum-based spent fuel inventoryincludes several different fuel forms and levels of235Uenrichment. Highly enriched fuels (235U enrichment
9、 levels20 %) are part of this inventory.1.3 Knowledge of the corrosion behavior of aluminum-based spent nuclear fuels is required to ensure safety and tosupport licensing or other approval activities, or both, neces-sary for disposal in a geologic repository. The response of thealuminum-based spent
10、nuclear fuel waste form(s) to disposalenvironments must be established for configuration-safetyanalyses, criticality analyses, PAs, and other analyses requiredto assess storage, treatment, transportation, and disposal ofspent nuclear fuels. This is particularly important for the highlyenriched, alum
11、inum-based spent nuclear fuels. The test proto-cols described in this guide are designed to establish materialresponse under the repository-relevant conditions.1.4 The majority of the aluminum-based spent nuclear fuelsare aluminum clad, aluminum-uranium alloys. The aluminum-uranium alloy typically c
12、onsists of uranium aluminide particlesdispersed in an aluminum matrix. Other aluminum-based fuelsinclude dispersions of uranium oxide, uranium silicide, oruranium carbide particles in an aluminum matrix. Theseparticles, including the aluminides, are generally cathodic tothe aluminum matrix. Selectiv
13、e leaching of the aluminum inthe exposure environment may provide a mechanism forredistribution and relocation of the uranium-rich particles.Particle redistribution tendencies will depend on the nature ofthe aluminum corrosion processes and the size, shape, distri-bution and relative reactivity of t
14、he uranium-rich particles.Interpretation of test data will require an understanding of thematerial behavior. This understanding will enable evaluation ofthe design and configuration of the waste package to ensurethat unfilled regions in the waste package do not provide sitesfor the relocation of the
15、 uranium-rich particles into nuclearcritical configurations. Test samples must be evaluated, prior totesting, to ensure that the size and shape of the uranium-richparticles in the test samples are representative of the particlesin the waste form being evaluated.1.5 The use of the data obtained by th
16、e testing described inthis guide will be optimized to the extent the samples mimicthe condition of the waste form during actual repositoryexposure. The use of Practice C1174 is recommended forguidance. The selection of test samples, which may be unagedor artificially aged, should ensure that the tes
17、t samples andconditions bound the waste form/repository conditions. Thetest procedures should carefully describe any artificial agingtreatment used in the test program and explain why thattreatment was selected.1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is t
18、he direct responsibility of C26.13 on Spent Fuel and High LevelWaste.Current edition approved Sept. 1, 2018. Published October 2018. Originallyapproved in 1999. Last previous edition approved in 2010 as C1431 99 (2010)1.DOI: 10.1520/C1431-99R18.Copyright ASTM International, 100 Barr Harbor Drive, PO
19、 Box 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 b
20、y the World Trade Organization Technical Barriers to Trade (TBT) Committee.11.6 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and
21、Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:2C1174 Practice for Evaluation of the Long-Term Behavior ofMaterials Used in Engineered Barrier Systems (EBS) forGeological Disposal of High-Level Radioactive
22、Waste2.2 Government Documents10 CFR 60 US Code of Federal Regulations Title 10, Part60, Disposal of High Level Radioactive Wastes in Geo-logic Repositories10 CFR 71 US Code of Federal Regulations Title 10, Part71, Packaging and Transport of Radioactive Materials10 CFR 72 US Code of Federal Regulatio
23、ns Title 10, Part72, Licensing Requirements for the Independent Storageof Spent Nuclear and High-Level Radioactive Waste3. Terminology3.1 Definitions:3.1.1 Terms used in this guide are defined in PracticeC1174, by common usage, by Websters New WorldDictionary, or as described in 3.2, or combination
24、thereof.3.2 Definitions:3.2.1 aluminum-based spent nuclear fuelirradiatednuclear fuel or target elements or assemblies, or both, that areclad in aluminum or aluminum-rich alloys. The microstruc-tures contain a continuous aluminum-rich matrix withuranium-rich particles dispersed in this matrix.3.2.2
25、aluminum-based spent nuclear fuel form or wasteformany metallic form produced from aluminum-based spentnuclear fuel and having a microstructure containing a continu-ous aluminum-rich matrix with uranium-rich particles dis-persed in this matrix. This term may include the fuel itself.3.2.3 artificial
26、agingany short time treatment that isdesigned to duplicate or simulate the material/property changesthat normally occur after prolonged exposure and radioactivedecay.3.2.4 attribute testa test conducted to provide materialproperties that are required as input to behavior models, butthat are not them
27、selves responses to the environment.3.2.5 boundinga test, sample condition or calculationdesigned to provide an evaluation of the limits to materialbehavior under relevant conditions.3.2.6 characterization testin high-level radioactive wastemanagement, any test conducted principally to furnish infor
28、-mation for a mechanistic understanding of alteration.3.2.7 corrosion productan ion or compound formed dur-ing the interaction of the aluminum-based spent nuclear fuelwith its storage or disposal environment. The corrosion productmay be the result of aqueous corrosion, oxidation, reactionwith moist
29、air, or other types of chemical interaction.3.2.8 interim storage installationa facility designed tostore spent nuclear fuels for an extended period of time thatmeets the intent of the requirements of an independent spentfuel storage installation or a monitored retrievable storagefacility, as descri
30、bed in 10 CFR 72.3.2.9 melt-dilute processa process to lower the fraction of235U in highly enriched, aluminum-based spent nuclear fuel bymelting and adding depleted uranium to the waste from.3.2.10 performance assessmentan analysis that identifiesthe processes and events that might affect a disposal
31、 system,examines the effects of those processes and events on theperformance of the disposal system, and estimates the cumu-lative releases of radionuclides considering the associateduncertainties caused by all significant processes and events.3.2.11 safety analysisan analysis to determine the risk
32、tothe public health and safety associated with the storage,treatment, transportation, or disposal, or combination thereof,of aluminum-based spent nuclear fuel.3.2.12 service condition testa test of a material conductedunder conditions in which the values of the independentvariables characterizing th
33、e service environment are in therange expected in actual service.4. Significance and Use4.1 Disposition of aluminum-based spent nuclear fuel willinvolve:4.1.1 Removal from the existing storage or transfer facility,4.1.2 Characterization or treatment, or both, of the fuel orthe resulting waste form,
34、or both,4.1.3 Placement of the waste form in a canister,4.1.4 Placement of the canister in a safe and environmen-tally sound interim storage facility,4.1.5 Removal from the interim storage facility and trans-port to the repository,4.1.6 Placement in a waste container,4.1.7 Emplacement in the reposit
35、ory, and4.1.8 Repository closure and geologic disposal. Actions ineach of these steps may significantly impact the success of anysubsequent step.4.2 Aluminum-based spent nuclear fuel and the aluminum-based waste forms display physical and chemical characteris-tics that differ significantly from the
36、characteristics of commer-cial nuclear fuels and from high level radioactive wasteglasses. For example, some are highly enriched and most haveheterogeneous microstructures that include very small,uranium-rich particles. The impact of this difference on reposi-tory performance must be evaluated and u
37、nderstood.4.3 The U.S. Nuclear Regulatory Commission has licensingauthority over public domain transportation and repositorydisposal (and most of the interim dry storage) of spent nuclearfuels and high-level radioactive waste under the requirements2For referenced ASTM standards, visit the ASTM websi
38、te, 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.C1431 99 (2018)2established by 10 CFR 60, 10 CFR 71, and 10 CFR 72. Theserequirements outline specific informatio
39、n needs that should bemet through test protocols, for example, those mentioned inthis guide. The information developed from the tests describedin this guide is not meant to be comprehensive. However, thetests discussed here will provide corrosion property data tosupport the following information nee
40、ds.4.3.1 A knowledge of the solubility, leaching, oxidation/reduction reactions, and corrosion of the waste form constitu-ents in/by the repository environment (dry air, moist air, andrepository relevant water) (see 10 CFR 60.112 and 135).4.3.2 A knowledge of the effects of radiolysis and tempera-tu
41、re on the oxidation, corrosion, and leaching behavior (see 10CFR 60.135).4.3.3 A knowledge of the temperature dependence of thesolubility of waste form constituents plus oxidation and corro-sion products (see 10 CFR 60.135).4.3.4 Information from laboratory experiments or technicalanalyses, or both,
42、 about time dependence of the internalcondition of the waste package (see 10 CFR 60.143 and 10CFR 72.76).4.3.5 Laboratory demonstrations of the effects of the elec-trochemical differences between the aluminum-based wasteform and the candidate packaging materials on galvaniccorrosion (see 10 CFR 71.4
43、3) or the significance of electricalcontact between the waste form and the packaging materials onitems outlined in 4.3.1 4.3.4 (see 10 CFR 60.135), or both.4.3.6 Information on the risk involved in the receipt,handling, packaging, storage, and retrieval of the waste forms(see 10 CFR 72.3).4.3.7 Info
44、rmation on the physical and chemical condition ofthe waste form upon repository placement so that itemsoutlined in 4.3.1 4.3.4 can be evaluated (see 10 CFR 60.135).4.3.8 Knowledge of the degradation of the waste formduring interim storage so that operational safety problems withrespect to its remova
45、l from storage can be assessed, if suchremoval is necessary (see 10 CFR 72.123).4.3.9 Knowledge of the condition of the waste form prior torepository placement so that items outlined in 4.3.1 4.3.4 areproperly addressed (see 10 CFR 60.135).4.4 Conditions expected during each stage of the disposition
46、process must be addressed. Exposure conditions anticipatedover the interim storage through geologic disposition periodsinclude dry and moist air, and aqueous environments. The airenvironments are associated with interim storage and the earlystages of repository storage while the aqueous environments
47、arise after water intrusion into the repository has causedcorrosion-induced failure of the waste package.5. Information Relevant to Geologic Disposal5.1 Tests of the aluminum-based waste forms should, alongwith applicable and qualified data from the literature, or both,provide data pertinent to (a)
48、corrosion or oxidation of wasteform constituents in vapor environments, or both, (b) corrosionor oxidation of waste form constituents in liquid environments,or both, (c) dissolution of waste form constituents, (d) oxida-tion products or corrosion products, or both and (e) selectiveleaching of waste
49、form constituents. Selected tests shouldprovide data concerning:5.1.1 The effective release rates (as solute or colloidalspecies) and dissolution rates of waste form constituents andcorrosion products in water compositions relevant to repositorydisposal,5.1.2 The temperature dependence of, and the effect ofradiolysis products on, waste form constituent solubility inrepository relevant water compositions,5.1.3 The corrosion rate or relative corrosion rates of thevarious constituents in the waste form, or both,5.1.4 An understanding of the effect of waste form micr
