1、Designation: C 1174 07Standard 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 C 1174; the number immediately follo
2、wing 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 (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 This practice de
3、scribes 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 geologic repository
4、. 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 initiallyimmobilize
5、d), 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, and model conf
6、irmation.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 categorizedaccording to the in
7、formation 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 materials proper-ties,1.1.3.2 Characterization tests to measure the effects ofmaterial and environmental variables on behav
8、ior,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 disposalconditions,1.1.3.
9、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 practice is to
10、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 in materia
11、lsbehavior 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 practices and d
12、etermine the applica-bility of regulatory requirements prior to use.2. Referenced Documents2.1 ASTM Standards:2C 1285 Test Methods for Determining Chemical Durabilityof Nuclear, Hazardous, and Mixed Waste Glasses andMultiphase Glass Ceramics: The Product Consistency Test(PCT)E 177 Practice for Use o
13、f the Terms Precision and Bias inASTM Test MethodsE 178 Practice for Dealing With Outlying ObservationsE 583 Practice for Systematizing the Development of(ASTM) Voluntary Consensus Standards for the Solutionof Nuclear and Other Complex Problems32.2 ANSI Standard:41This practice is under the jurisdic
14、tion 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 June 1, 2007. Published August 2007. Originallyapproved in 1991. Last previous edition approved in 2004 as C 1174 04.2For referenced ASTM
15、 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.3Withdrawn.4Available from American National Standards Institute (ANSI), 25 W. 43
16、rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.ANSI/ASME NQA-1 Quality Assurance Program Require-ments for Nuclear Facility Applications2.3 U.S. Government Documents:DOE/RW-03
17、33P, Assurance 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-L
18、evel Radioactive Wastes in a Geologic Repositoryat Yucca Mountain, Nevada, U.S. Nuclear RegulatoryCommission, latest revision5Code of Federal Regulations Title 40, Part 191, Environ-mental Radiation Protection Standards for Managementand Disposal of Spent Nuclear Fuel, High-Level andTransuranic Radi
19、oactive 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 General Definitions:3.1.1 Terminology used in this practice is per existingASTM defini
20、tions, or as understood 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 st
21、andard and is 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 highlyradioa
22、ctive material 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 r
23、epositorya system 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 im
24、portant to safetyrefers 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 des
25、ign basis events; 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
26、 barriers whose 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
27、nuclear fuel and 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 absor
28、bent materials 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 interpre
29、tation activitiesconducted 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
30、 that is performed 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, a
31、nalyses, reactor 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-informedrefer
32、s to an approach 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 barriersyst
33、em material that 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 complian
34、ce period weighted by the prob-ability of occurrence. (10 CFR 63.113)3.3 Definitions of Terms Specific to This StandardThefollowing definitions are defined only for the usage in thisstandard, and for the explanation of the analyses containedherein.3.3.1 accelerated testa test that results in an incr
35、ease inthe rate of an alteration mode or in the extent of reactionprogress, when compared with expected service conditions.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 Compilati
36、on of ASTM Standard Definitions, available from ASTM Head-quarters, 100 Barr Harbor Drive, West Conshohocken, PA 19428.C1174072Changes in the expected alteration mechanism(s) caused by theaccelerated test conditions, if any, must be accounted for in theuse of the accelerated test data.3.3.2 alterati
37、onany change in the form, state, or proper-ties of a material.3.3.3 alteration mechanismthe fundamental chemical orphysical processes by which alteration occurs.3.3.4 alteration modea particular form of alteration, forexample, dissolution or passivation.3.3.5 analoga material, process, or system who
38、se compo-sition and environmental history are sufficiently similar to thatanticipated for the materials of interest to permit use of insightgained regarding its condition or behavior to be applied to amaterial, process, or system of interest.3.3.6 attribute testa test conducted to provide materialpr
39、operties that are required as input to behavior models, butthat are not themselves responses to the environment. Ex-amples are density, thermal conductivity, mechanical proper-ties, radionuclide content of waste forms, etc.3.3.7 behaviorthe response of a material to the environ-ment in which it is p
40、laced.3.3.8 bounding modela model that yields values fordependent variables or effects that are expected to be eitheralways greater than or always less than those expected for thevariables or effects to be bounded.3.3.9 characterization testin high-level radioactive wastemanagement, any test or anal
41、ysis conducted principally tofurnish information used to determine parameter values for amodel or develop a mechanistic understanding of alteration.Examples include polarization tests, solubility measurements,etc.3.3.10 confirmation testa test in which results are notused in the initial development
42、of a model or the determinationof parameter values for a model but are used for comparisonwith the predictions of that model for model validation.3.3.11 degradationany change in a material that ad-versely affects the behavior of that material or its ability toperform its intended function; adverse a
43、lteration.3.3.12 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 directfit of the experimental data such as a regression analysis or maybe developed as a model which encompasses all the obse
44、rveddata points; that is, a bounding model.3.3.13 extrapolationthe act of predicting long-term mate-rial behavior beyond the range of data collected by empiricalobservation in short-term tests.3.3.14 in-situ testa test conducted in the geologic envi-ronment in which a material or waste form will be
45、emplaced.3.3.15 modela simplified representation of a system orphenomenon, based on a set of hypotheses (assumptions, data,simplifications, and/or idealizations) that describe the systemor explain the phenomenon, often expressed mathematically.3.3.16 predictdeclare in advance the behavior of a mate-
46、rial on the basis of a model.3.3.17 mechanistic modelmodel derived from acceptedfundamental laws governing the behavior of matter and energy.It corresponds to one end of a spectrum of models with varyingdegrees of empiricism.3.3.18 pyrophoriccapable of igniting spontaneously un-der temperature, chem
47、ical, or physical/mechanical conditionsspecific to the storage, handling, or transportation environment3.3.19 semi-empirical modela model based partially on amechanistic understanding and partially on empirical fits todata from experiments.3.3.20 service condition testa test with a material that isc
48、onducted under conditions in which the values of the inde-pendent variables characterizing the service environment arewithin the range expected in actual service.3.3.21 model validationthe process through which modelpredictions are compared with independent measurements oranalyses to provide confide
49、nce 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 is used to provide bounding values forthe alteration behavior, may be regarded as validated for itsintended usage.4. Summary
