ASTM C1174-2017 Standard Practice for Evaluation of the Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive W.pdf

1、Designation: C1174 07 (Reapproved 2013)C1174 17Standard Practice forPredictionEvaluation of the Long-Term Behavior ofMaterials, Including Waste Forms, Materials Used inEngineered Barrier Systems (EBS) for Geological Disposalof High-Level Radioactive Waste1This standard is issued under the fixed desi

2、gnation C1174; the number immediately 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

3、or reapproval.1. Scope1.1 This practice describes addresses how various test methods and data analyses can be used to develop models for thepredictionevaluation of the long-term alteration behavior of materials, such asmaterials used in engineered barrier system (EBS)materials and waste forms, used

4、in the geologic for the disposal of spent nuclear fuel (SNF) and other high-level nuclear wastein a geologic repository. The alteration behavior of waste formforms and EBS materials is important because it affects the retentionof radionuclides by the disposal system. The waste form and EBS materials

5、 provide a barrier to release either directly (aswithinthe disposal system either directly, as in the case of waste forms in which the radionuclides are initially immobilized),immobilized,or indirectly (asindirectly, as in the case of EBS containment materials that restrict the ingress of groundwate

6、r or the egress ofradionuclides that are released as the waste forms and EBS materials degrade).degrade.1.1.1 Steps involved in making such predictions include problem definition, testing, modeling, and model confirmation.1.1.2 The predictions are based on models derived from theoretical considerati

7、ons, expert judgment, interpretation of dataobtained from tests, and appropriate analogs.1.1.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used formodel development and use. These tests may include but are not limited to the followi

8、ng:1.1.3.1 Attribute tests to measure intrinsic materials properties,1.1.3.2 Characterization tests to measure the effects of material and environmental variables on behavior,1.1.3.3 Accelerated tests to accelerate alteration and determine important mechanisms and processes that can affect theperfor

9、mance of waste form and EBS materials,1.1.3.4 Service condition tests to confirm the appropriateness of the model and variables for anticipated disposal conditions,1.1.3.5 Confirmation tests to verify the predictive capacity of the model, and1.1.3.6 Tests or analyses performed with analog materials

10、to identify important mechanisms, verify the appropriateness of anaccelerated test method, and to confirm long-term model predictions.1.2 The purpose of this practice is to provide a scientifically-based strategy for developing models that can be used to estimatematerial alteration behavior after a

11、repository is permanently closed (that is, the post-closure period) because the timescalesinvolved with geological disposal preclude direct validation of predictions.1.3 The purpose of this practice is to provide methods for developing models that can be used for the prediction of materialsbehavior

12、over the long periods of time pertinent to the service life of a geologic repository as part of the basis for performanceassessment of the repository. This practice also addresses uncertainties in materials behavior models and the impact on theconfidence in the EBS design criteria, the scientific ba

13、ses of alteration models, and repository performance assessments using thosemodels. This includes the identification and use of conservative assumptions to address uncertainty in the long-term performanceof materials.1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials

14、 include problem definition, laboratory andfield testing, modeling of individual and coupled processes, and model confirmation.1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations,expert judgments, and interpretations of data obta

15、ined from tests and analyses of appropriate analogs.1 This practice 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 HighLevel Waste.Current edition approved April 1, 2013July 1, 2017. Published April 2013

16、August 2017. Originally approved in 1991. Last previous edition approved in 20072013 asC1174 07.C1174 07 (2013). DOI: 10.1520/C1174-07R13.10.1520/C1174-17.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 t

17、o 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.Copyrig

18、ht ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States11.3.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used formodel development, support, and use. These tests may include but ar

19、e not limited to: accelerated tests, attribute tests,characterization tests, confirmation tests, and service condition tests.1.3 This practice also addresses uncertainties in materials behavior models and their impact on the confidence in theperformance assessment.1.4 This standard does not purport

20、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 regulatoryrequirements prior to use.1.5 This international standard was developed in ac

21、cordance 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 Technical Barriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM

22、 Standards:2C859 Terminology Relating to Nuclear MaterialsC1285 Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and MultiphaseGlass Ceramics: The Product Consistency Test (PCT)C1682 Guide for Characterization of Spent Nuclear Fuel in Support of Interim

23、 Storage, Transportation and Geologic RepositoryDisposalE177 Practice for Use of the Terms Precision and Bias in ASTM Test MethodsE178 Practice for Dealing With Outlying ObservationsE583 Practice for Systematizing the Development of (ASTM) Voluntary Consensus Standards for the Solution of Nuclear an

24、dOther Complex Problems (Withdrawn 1996)32.2 ANSI Standard:4ANSI/ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facility Applications2.3 U.S. Government Documents:DOE/RW-0333P, Assurance Requirements and Description, USDOE OCRWM, latest revisionCode of Federal Regulations, Title 10, P

25、art 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, U.S.Nuclear Regulatory Commission, January 199755NOTE 1The U.S. government documents listed in 2.3 and referenced in this practice are only included as examples of local regulations that, dependingon the location of the disp

26、osal site, may or may not be appropriate. Users of this practice should adhere to the regulatory documents and regulationsapplicable in the licensing location. The references listed below are explicit examples of local regulations.Code of Federal Regulations, Title 10, Part 63, Disposal of High-Leve

27、l Radioactive Wastes in a Geologic Repository at YuccaMountain, Nevada, U.S. Nuclear Regulatory Commission, latest revisionCode of Federal Regulations Title 40, Part 191, Environmental Radiation Protection Standards for Management and Disposalof Spent Nuclear Fuel, High-Level and Transuranic Radioac

28、tive Wastes, July 20025Public Law 97-425, Nuclear Waste Policy Act of 1982, as amendedNUREG0856, Final Technical Position on Documentation of Computer Codes for High-Level Waste Management (1983)2.4 International Documents:SKI Report 99:2 Regulatory Perspectives on Model Validation in High-Level Rad

29、ioactive Waste Programs: A Joint NRC/SKIWhite Paper, Swedish Nuclear Power Inspectorate, March 19996IAEA SSR-5 Disposal of Radioactive Waste Specific Safety Requirements, International Atomic Energy Agency (IAEA),Vienna, Austria, 20116IAEA GSG-3 The Safety Case and Safety Assessment for the Predispo

30、sal Management of Radioactive Waste, InternationalAtomic Energy Agency (IAEA), Vienna, Austria 20136SSMFS 2008:37 Swedish Radiation Safety Authority Regulatory Code General Advice, Swedish Radiation Safety Authority,Stockholm, January 30, 20097Finland Government Decree (736/2008) on the Safety of Di

31、sposal of Nuclear Waste, Radiation and Nuclear Safety Authority inFinland (STUK) Helsinki, November 27, 200882 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the stan

32、dards Document Summary page on the ASTM website.3 The last approved version of this historical standard is referenced on www.astm.org.4 Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http:/www.ansi.org.5 Available from U.S. Government Prin

33、ting Office, Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401,20401-0001,http:/www.access.gpo.gov.6 Available from International Atomic Energy Agency (IAEA), Vienna International Centre, PO Box 100, A-1400 Vienna, Austria, www.iaea.org.7 Available from Swedis

34、h Radiation Safety Authority (SSMFS), Solna Strandvag 96, 171 16 Stockholm, www.stralsakerhetsmyndigheten.se.8 Available from Finlex, www.finlex.fi/en/.C1174 1723. Terminology3.1 Definitions:3.1.1 Terminology used in this practice is per existing ASTM definitions, or as understood per the common Eng

35、lish dictionarydefinitions, except as described below.3.1 Regulatory Definitions9and Other Published DefinitionsDefinitions used in this practice are as currently existing inTerminology C859of the particular terms below are based on the referenced Code of Federal Regulations, 10 CFR 63 and/or 10CFR

36、Part 60 which is pertinent to this standard and is under jurisdiction of the Nuclear Regulatory Commission (NRC). If preciseregulatory definitions are needed, the user should consult the appropriate governing reference., or as commonly accepted indictionaries of the English language, except for thos

37、e terms defined below for the specific usage of this practice.3.2.1 disposalthe emplacement in a repository of high-level radioactive waste, spent nuclear fuel, or other highly radioactivematerial with no foreseeable intent of recovery, whether or not such emplacement permits the recovery of such wa

38、ste.3.2.2 engineered barrier system (EBS)the waste packages and the underground facility, which means the undergroundstructure including openings and backfill materials.3.2.3 geologic repositorya system which is intended to be used for, or may be used for, the disposal of radioactive wastes inexcava

39、ted geologic media. A geologic repository includes the geologic repository operations area, and the portion of the geologicsetting that provides isolation of the radioactive waste.3.2.4 important to safetyrefers to those engineered features of the geologic repository operations area whose function i

40、s: (1)To provide reasonable assurance that high level waste can be received, handled, packaged, stored, emplaced, and retrieved withoutexceeding regulatory requirements for Category 1 design basis events; or (2) To prevent or mitigate Category 2 design basis eventsthat could result in doses equal to

41、 or greater than the regulatory values to any individual located on or beyond any point on theboundary of the site.3.2.5 important to waste isolationrefers to those engineered and natural barriers whose function is to provide reasonableassurance that high-level waste can be disposed without exceedin

42、g the regulatory requirements.3.2.6 high-level radioactive waste, (HLW)includes spent nuclear fuel and solid wastes obtained on conversion of wastesresulting from the reprocessing of spent nuclear fuel and other wastes as approved by the NRC for disposal in a deep geologicrepository.3.2.7 waste form

43、the radioactive waste materials and any encapsulating or stabilizing matrix in which it is incorporated.3.2.8 waste packagethe waste form and any containers, shielding, packing and other absorbent materials immediatelysurrounding an individual waste container.3.2.9 datainformation developed as a res

44、ult of scientific investigation activities , including information acquired in field orlaboratory tests, extracted from reference sources, and the results of reduction, manipulation, or interpretation activities conductedto prepare it for use as input in analyses, models or calculations used in perf

45、ormance assessment, integrated safety analyses, thedesign process, performance confirmation, and other similar work.3.2.10 scientific investigationany research, experiment, test, study, or activity that is performed for the purpose ofinvestigating the material aspects of a geologic repository, inclu

46、ding the investigations that support design of the facilities, thewaste package and performance models.3.2.11 technical informationinformation available from drawings, specifications, calculations, analyses, reactor operationalrecords, fabrication and construction records, other design basis documen

47、ts, regulatory or program requirements documents, orconsensus codes and standards that describe physical, performance, operational, or nuclear characteristics or requirements.3.2.12 risk-informedrefers to an approach to the licensing of a geologic repository based on the understanding that some risk

48、will always exist and that the engineered barrier system and natural barrier system are designed to perform such that the risk isacceptable.3.2.13 risk-significantpertaining to an engineered barrier system material that has been determined to have a significant effecton the performance of the reposi

49、tory during the regulatory compliance period after closure.3.2.14 boundary dose riskthe quantitative estimate of the expected annual dose to an individual at the repository site boundaryover the compliance period weighted by the probability of occurrence. (10 CFR 63.113)3.2 Regulatory and Other Published DefinitionsDefinitions of the particular terms below are generally consistent with theusage of these terms in the context of geological disposal of radioactive materials. If precise regulatory definitions are needed, theuser should consult the appropriat