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

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

25、ts; or (2) To prevent or mitigateCategory 2 design basis events that could result in doses equalto or greater than the regulatory values to any individuallocated on or beyond any point on the boundary of the site.3.2.5 important to waste isolationrefers to those engi-neered and natural barriers whos

26、e function is to providereasonable assurance that high-level waste can be disposedwithout exceeding the regulatory requirements.3.2.6 high-level radioactive waste, (HLW)includes spentnuclear fuel and solid wastes obtained on conversion of wastesresulting from the reprocessing of spent nuclear fuel a

27、nd otherwastes as approved by the NRC for disposal in a deep geologicrepository.3.2.7 waste formthe radioactive waste materials and anyencapsulating or stabilizing matrix in which it is incorporated.3.2.8 waste packagethe waste form and any containers,shielding, packing and other absorbent materials

28、 immediatelysurrounding an individual waste container.3.2.9 datainformation developed as a result of scientificinvestigation activities , including information acquired in fieldor laboratory tests, extracted from reference sources, and theresults of reduction, manipulation, or interpretation activit

29、iesconducted to prepare it for use as input in analyses, models orcalculations used in performance assessment, integrated safetyanalyses, the design process, performance confirmation, andother similar work.3.2.10 scientific investigationany research, experiment,test, study, or activity that is perfo

30、rmed for the purpose ofinvestigating the material aspects of a geologic repository,including the investigations that support design of the facilities,the waste package and performance models.3.2.11 technical informationinformation available fromdrawings, specifications, calculations, analyses, react

31、or opera-tional records, fabrication and construction records, otherdesign basis documents, regulatory or program requirementsdocuments, or consensus codes and standards that describephysical, performance, operational, or nuclear characteristicsor requirements.3.2.12 risk-informedrefers to an approa

32、ch to the licensingof a geologic repository based on the understanding that somerisk will always exist and that the engineered barrier systemand natural barrier system are designed to perform such that therisk is acceptable.3.2.13 risk-significantpertaining to an engineered barriersystem material th

33、at has been determined to have a significanteffect on the performance of the repository during the regula-tory compliance period after closure.3.2.14 boundary dose riskthe quantitative estimate of theexpected annual dose to an individual at the repository siteboundary over the compliance period weig

34、hted by the prob-ability of occurrence. (10 CFR 63.113)3.3 Definitions of Terms Specific to This Standard:3.3.1 The following definitions are defined only for theusage in this standard, and for the explanation of the analysescontained herein.4Available from American National Standards Institute (ANS

35、I), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.5Available 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.6See Compilation of ASTM Standard Definitions, available from ASTMHe

36、adquarters, 100 Barr Harbor Drive, West Conshohocken, PA 19428.C1174 07 201323.3.2 accelerated testa test that results in an increase inthe rate of an alteration mode or in the extent of reactionprogress, when compared with expected service conditions.Changes in the expected alteration mechanism(s)

37、caused by theaccelerated test conditions, if any, must be accounted for in theuse of the accelerated test data.3.3.3 alterationany change in the form, state, or proper-ties of a material.3.3.4 alteration mechanismthe fundamental chemical orphysical processes by which alteration occurs.3.3.5 alterati

38、on modea particular form of alteration, forexample, dissolution or passivation.3.3.6 analoga material, process, or system whose compo-sition and environmental history are sufficiently similar to thatanticipated for the materials of interest to permit use of insightgained regarding its condition or b

39、ehavior to be applied to amaterial, process, or system of interest.3.3.7 attribute testa test conducted to provide materialproperties that are required as input to behavior models, butthat are not themselves responses to the environment. Ex-amples are density, thermal conductivity, mechanicalpropert

40、ies, radionuclide content of waste forms, etc.3.3.8 behaviorthe response of a material to the environ-ment in which it is placed.3.3.9 bounding modela model that yields values for de-pendent variables or effects that are expected to be eitheralways greater than or always less than those expected for

41、 thevariables or effects to be bounded.3.3.10 characterization testin high-level radioactivewaste management, any test or analysis conducted principallyto furnish information used to determine parameter values fora model or develop a mechanistic understanding of alteration.Examples include polarizat

42、ion tests, solubility measurements,etc.3.3.11 confirmation testa test in which results are not usedin the initial development of a model or the determination ofparameter values for a model but are used for comparison withthe predictions of that model for model validation.3.3.12 degradationany change

43、 in a material that adverselyaffects the behavior of that material or its ability to perform itsintended function; adverse alteration.3.3.13 empirical modela model based only on observa-tions or data from experiments, without regard to mechanismor theory. An empirical model may be developed from a d

44、irectfit of the experimental data such as a regression analysis or maybe developed as a model which encompasses all the observeddata points; that is, a bounding model.3.3.14 extrapolationthe act of predicting long-term mate-rial behavior beyond the range of data collected by empiricalobservation in

45、short-term tests.3.3.15 in-situ testa test conducted in the geologic envi-ronment in which a material or waste form will be emplaced.3.3.16 modela simplified representation of a system orphenomenon, based on a set of hypotheses (assumptions, data,simplifications, and/or idealizations) that describe

46、the systemor explain the phenomenon, often expressed mathematically.3.3.17 predictdeclare in advance the behavior of a mate-rial on the basis of a model.3.3.18 mechanistic modelmodel derived from acceptedfundamental laws governing the behavior of matter and energy.It corresponds to one end of a spec

47、trum of models with varyingdegrees of empiricism.3.3.19 pyrophoriccapable of igniting spontaneously un-der temperature, chemical, or physical/mechanical conditionsspecific to the storage, handling, or transportation environment3.3.20 semi-empirical modela model based partially on amechanistic unders

48、tanding and partially on empirical fits todata from experiments.3.3.21 service condition testa test with a material that isconducted under conditions in which the values of the inde-pendent variables characterizing the service environment arewithin the range expected in actual service.3.3.22 model v

49、alidationthe process through which modelpredictions are compared with independent measurements oranalyses to provide confidence that a model accurately predictsthe alteration behavior of waste package/EBS materials underparticular sets of credible environmental conditions. Thisprovides confidence in the capability of the model to predictalteration behavior under conditions or durations that have notbeen tested directly. An alteration model that has been demon-strated to provide bounding results under all credible environ-mental conditions, and