ASTM C1174-2007(2013) Standard Practice for Prediction of the Long-Term Behavior of Materials Including Waste Forms Used in Engineered Barrier Systems (EBS) for Geological Disposal.pdf
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1、Designation: C1174 07 Reapproved 2013Standard Practice forPrediction of the Long-Term Behavior of Materials, IncludingWaste Forms, Used in Engineered Barrier Systems (EBS) forGeological Disposal of High-Level Radioactive Waste1This standard is issued under the fixed designation C1174; the number imm
2、ediately following the designation indicates the year oforiginal 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 Thi
3、s practice describes test methods and data analysesused to develop models for the prediction of the long-termbehavior of materials, such as engineered barrier system (EBS)materials and waste forms, used in the geologic disposal ofspent nuclear fuel (SNF) and other high-level nuclear waste ina geolog
4、ic repository. The alteration behavior of waste formand EBS materials is important because it affects the retentionof radionuclides by the disposal system. The waste form andEBS materials provide a barrier to release either directly (as inthe case of waste forms in which the radionuclides are initia
5、llyimmobilized), or indirectly (as in the case of containmentmaterials that restrict the ingress of groundwater or the egressof radionuclides that are released as the waste forms and EBSmaterials degrade).1.1.1 Steps involved in making such predictions includeproblem definition, testing, modeling, a
6、nd model confirmation.1.1.2 The predictions are based on models derived fromtheoretical considerations, expert judgment, interpretation ofdata obtained from tests, and appropriate analogs. 1.1.3 For thepurpose of this practice, tests1.1.3 For the purpose of this practice, tests are categorizedaccord
7、ing to the information they provide and how it is usedfor model development and use. These tests may include butare not limited to the following:1.1.3.1 Attribute tests to measure intrinsic materialsproperties,1.1.3.2 Characterization tests to measure the effects ofmaterial and environmental variabl
8、es on behavior,1.1.3.3 Accelerated tests to accelerate alteration and deter-mine important mechanisms and processes that can affect theperformance of waste form and EBS materials,1.1.3.4 Service condition tests to confirm the appropriate-ness of the model and variables for anticipated disposalcondit
9、ions,1.1.3.5 Confirmation tests to verify the predictive capacityof the model, and1.1.3.6 Tests or analyses performed with analog materials toidentify important mechanisms, verify the appropriateness ofan accelerated test method, and to confirm long-term modelpredictions.1.2 The purpose of this prac
10、tice is to provide methods fordeveloping models that can be used for the prediction ofmaterials behavior over the long periods of time pertinent tothe service life of a geologic repository as part of the basis forperformance assessment of the repository.1.3 This practice also addresses uncertainties
11、 in materialsbehavior models and their impact on the confidence in theperformance assessment.1.4 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 safety and health prac
12、tices and determine the applica-bility of regulatory requirements prior to use.2. Referenced Documents2.1 ASTM Standards:2C1285 Test Methods for Determining Chemical Durabilityof Nuclear, Hazardous, and Mixed Waste Glasses andMultiphase Glass Ceramics: The Product Consistency Test(PCT)E177 Practice
13、for Use of the Terms Precision and Bias inASTM Test MethodsE178 Practice for Dealing With Outlying ObservationsE583 Practice for Systematizing the Development of(ASTM) Voluntary Consensus Standards for the Solutionof Nuclear and Other Complex Problems (Withdrawn1996)31This practice is under the juri
14、sdiction of ASTM Committee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fueland High Level Waste.Current edition approved April 1, 2013. Published April 2013. Originallyapproved in 1991. Last previous edition approved in 2007 as C1174 07. DOI:10.1520/C117
15、4-07R13.2For 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.3The last approved version of this historical standar
16、d is referenced onwww.astm.org.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States12.2 ANSI Standard:4ANSI/ASME NQA-1 Quality Assurance Program Require-ments for Nuclear Facility Applications2.3 U.S. Government Documents:DOE/RW-0333P, Ass
17、urance Requirements and Description,USDOE OCRWM, latest revisionCode of Federal Regulations, Title 10, Part 60, Disposal ofHigh-Level Radioactive Wastes in Geologic Repositories,U.S. Nuclear Regulatory Commission, January 19975Code of Federal Regulations, Title 10, Part 63, Disposal ofHigh-Level Rad
18、ioactive Wastes in a Geologic Repositoryat Yucca Mountain, Nevada, U.S. Nuclear RegulatoryCommission, latest revision5Code of Federal Regulations Title 40, Part 191, Environmen-tal Radiation Protection Standards for Management andDisposal of Spent Nuclear Fuel, High-Level and Tran-suranic Radioactiv
19、e Wastes, July 20025Public Law 97-425, Nuclear Waste Policy Act of 1982, asamendedNUREG0856, Final Technical Position on Documentationof Computer Codes for High-Level Waste Management(1983)63. Terminology3.1 Definitions:3.1.1 Terminology used in this practice is per existingASTM definitions, or as u
20、nderstood per the common Englishdictionary definitions, except as described below.3.2 Regulatory and Other Published DefinitionsDefinitions of the particular terms below are based on thereferenced Code of Federal Regulations, 10 CFR 63 and/or 10CFR Part 60 which is pertinent to this standard and is
21、underjurisdiction of the Nuclear Regulatory Commission (NRC). Ifprecise regulatory definitions are needed, the user shouldconsult the appropriate governing reference.3.2.1 disposalthe emplacement in a repository of high-level radioactive waste, spent nuclear fuel, or other highlyradioactive material
22、 with no foreseeable intent of recovery,whether or not such emplacement permits the recovery of suchwaste.3.2.2 engineered barrier system (EBS)the waste packagesand the underground facility, which means the undergroundstructure including openings and backfill materials.3.2.3 geologic repositorya sys
23、tem which is intended to beused for, or may be used for, the disposal of radioactive wastesin excavated geologic media. A geologic repository includesthe geologic repository operations area, and the portion of thegeologic setting that provides isolation of the radioactivewaste.3.2.4 important to saf
24、etyrefers to those engineered fea-tures of the geologic repository operations area whose functionis: (1) To provide reasonable assurance that high level wastecan be received, handled, packaged, stored, emplaced, andretrieved without exceeding regulatory requirements for Cat-egory 1 design basis even
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