ASTM C1174-07(2013)
(Practice)Standard Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
Standard Practice for Prediction of the Long-Term Behavior of Materials, Including Waste Forms, Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
SIGNIFICANCE AND USE
5.1 This practice supports the development of materials behavior models that can be used to predict alterations in materials over the very long time periods pertinent to the operation of a high-level nuclear waste repository; periods of time much longer than can be tested directly. Under the very extended service periods relevant to geological disposal—much longer periods than those encountered in normal engineering practice—equilibrium or steady state conditions may be achieved and models for reaction kinetics may be replaced by models, if justified, describing equilibrium extents of alteration. This practice is intended for use for waste form materials and materials proposed for use in an EBS that is designed to contain radionuclides released from high-level nuclear waste forms as they degrade over tens of thousands of years and more. Various U.S. Government regulations pertinent to repository disposal in the United States are as follows:
5.1.1 Public Law 97–425, the Nuclear Waste Policy Act of 1982, provides for the deep geologic disposal of high-level radioactive waste through a system of multiple barriers. The radiation release limits are to be set by the U.S. Environmental Protection Agency (EPA) (40 CFR 191). Licensing of such disposal will be done by the U.S. Nuclear Regulatory Commission (NRC).
5.1.2 The analyses described in this Standard Guide can be used to support the demonstration of compliance of the EBS components and design to the applicable requirements of 10 CFR 60 (pertaining to any HLW repository in the U.S.) and 10 CFR 63 (pertaining to the planned HLW repository at Yucca Mountain, NV).
5.1.2.1 10 CFR 60.135 and 60.113 require that the waste form be a material that is solid, non-particulate, non-pyrophoric, and non-chemically reactive, and that the waste package contain no liquid, particulates, chemically reactive or combustible materials and that the materials/components of the EBS be designed to provide – assuming anticipated processe...
SCOPE
1.1 This practice describes test methods and data analyses used to develop models for the prediction of the long-term behavior of materials, such as engineered barrier system (EBS) materials and waste forms, used in the geologic disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste form and EBS materials is important because it affects the retention of radionuclides by the disposal system. The waste form and EBS materials provide a barrier to release either directly (as in the case of waste forms in which the radionuclides are initially immobilized), or indirectly (as in the case of containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms and EBS materials 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 considerations, expert judgment, interpretation of data obtained from tests, and appropriate analogs. 1.1.3 For the purpose of this practice, tests
1.1.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used for model development and use. These tests may include but are not limited to the following:
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 the performance 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, and
1.1.3.6 Tes...
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Designation: C1174 − 07 (Reapproved 2013)
Standard Practice for
Prediction of the Long-Term Behavior of Materials, Including
Waste Forms, Used in Engineered Barrier Systems (EBS) for
Geological Disposal of High-Level Radioactive Waste
This standard is issued under the fixed designation C1174; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 1.1.3.5 Confirmation tests to verify the predictive capacity
of the model, and
1.1 This practice describes test methods and data analyses
1.1.3.6 Tests or analyses performed with analog materials to
used to develop models for the prediction of the long-term
identify important mechanisms, verify the appropriateness of
behavior of materials, such as engineered barrier system (EBS)
an accelerated test method, and to confirm long-term model
materials and waste forms, used in the geologic disposal of
predictions.
spent nuclear fuel (SNF) and other high-level nuclear waste in
a geologic repository. The alteration behavior of waste form 1.2 The purpose of this practice is to provide methods for
and EBS materials is important because it affects the retention developing models that can be used for the prediction of
of radionuclides by the disposal system. The waste form and materials behavior over the long periods of time pertinent to
EBS materials provide a barrier to release either directly (as in the service life of a geologic repository as part of the basis for
the case of waste forms in which the radionuclides are initially performance assessment of the repository.
immobilized), or indirectly (as in the case of containment
1.3 This practice also addresses uncertainties in materials
materials that restrict the ingress of groundwater or the egress
behavior models and their impact on the confidence in the
of radionuclides that are released as the waste forms and EBS
performance assessment.
materials degrade).
1.4 This standard does not purport to address all of the
1.1.1 Steps involved in making such predictions include
safety concerns, if any, associated with its use. It is the
problem definition, testing, modeling, and model confirmation.
responsibility of the user of this standard to establish appro-
1.1.2 The predictions are based on models derived from
priate safety and health practices and determine the applica-
theoretical considerations, expert judgment, interpretation of
bility of regulatory requirements prior to use.
data obtained from tests, and appropriate analogs.
1.1.3 For the purpose of this practice, tests are categorized
2. Referenced Documents
according to the information they provide and how it is used
for model development and use. These tests may include but 2.1 ASTM Standards:
are not limited to the following: C1285 Test Methods for Determining Chemical Durability
1.1.3.1 Attribute tests to measure intrinsic materials of Nuclear, Hazardous, and Mixed Waste Glasses and
properties, MultiphaseGlassCeramics:TheProductConsistencyTest
1.1.3.2 Characterization tests to measure the effects of (PCT)
E177 Practice for Use of the Terms Precision and Bias in
material and environmental variables on behavior,
1.1.3.3 Accelerated tests to accelerate alteration and deter- ASTM Test Methods
E178 Practice for Dealing With Outlying Observations
mine important mechanisms and processes that can affect the
performance of waste form and EBS materials, E583 Practice for Systematizing the Development of
(ASTM) Voluntary Consensus Standards for the Solution
1.1.3.4 Service condition tests to confirm the appropriate-
ness of the model and variables for anticipated disposal of Nuclear and Other Complex Problems (Withdrawn
1996)
conditions,
1 2
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
and High Level Waste. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved April 1, 2013. Published April 2013. Originally the ASTM website.
approved in 1991. Last previous edition approved in 2007 as C1174 – 07. DOI: The last approved version of this historical standard is referenced on
10.1520/C1174-07R13. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1174 − 07 (2013)
2.2 ANSI Standard: is: (1) To provide reasonable assurance that high level waste
ANSI/ASME NQA-1 Quality Assurance Program Require- can be received, handled, packaged, stored, emplaced, and
ments for Nuclear Facility Applications retrieved without exceeding regulatory requirements for Cat-
egory 1 design basis events; or (2) To prevent or mitigate
2.3 U.S. Government Documents:
Category 2 design basis events that could result in doses equal
DOE/RW-0333P, Assurance Requirements and Description,
to or greater than the regulatory values to any individual
USDOE OCRWM, latest revision
located on or beyond any point on the boundary of the site.
Code of Federal Regulations, Title 10, Part 60, Disposal of
3.2.5 important to waste isolation—refers to those engi-
High-Level Radioactive Wastes in Geologic Repositories,
neered and natural barriers whose function is to provide
U.S. Nuclear Regulatory Commission, January 1997
reasonable assurance that high-level waste can be disposed
Code of Federal Regulations, Title 10, Part 63, Disposal of
without exceeding the regulatory requirements.
High-Level Radioactive Wastes in a Geologic Repository
at Yucca Mountain, Nevada, U.S. Nuclear Regulatory 3.2.6 high-level radioactive waste, (HLW)—includes spent
nuclear fuel and solid wastes obtained on conversion of wastes
Commission, latest revision
CodeofFederalRegulationsTitle40,Part191, Environmen- resulting from the reprocessing of spent nuclear fuel and other
wastes as approved by the NRC for disposal in a deep geologic
tal Radiation Protection Standards for Management and
repository.
Disposal of Spent Nuclear Fuel, High-Level and Tran-
3.2.7 waste form—the radioactive waste materials and any
suranic Radioactive Wastes, July 2002
Public Law 97-425, Nuclear Waste Policy Act of 1982, as encapsulating or stabilizing matrix in which it is incorporated.
amended 3.2.8 waste package—the waste form and any containers,
NUREG–0856, Final Technical Position on Documentation shielding, packing and other absorbent materials immediately
of Computer Codes for High-Level Waste Management surrounding an individual waste container.
(1983)
3.2.9 data—information developed as a result of scientific
investigation activities , including information acquired in field
3. Terminology
or laboratory tests, extracted from reference sources, and the
results of reduction, manipulation, or interpretation activities
3.1 Definitions:
conducted to prepare it for use as input in analyses, models or
3.1.1 Terminology used in this practice is per existing
calculations used in performance assessment, integrated safety
ASTM definitions, or as understood per the common English
analyses, the design process, performance confirmation, and
dictionary definitions, except as described below.
other similar work.
3.2 Regulatory and Other Published Definitions—
3.2.10 scientific investigation—any research, experiment,
Definitions of the particular terms below are based on the
referenced Code of Federal Regulations, 10 CFR 63 and/or 10 test, study, or activity that is performed for the purpose of
investigating the material aspects of a geologic repository,
CFR Part 60 which is pertinent to this standard and is under
jurisdiction of the Nuclear Regulatory Commission (NRC). If includingtheinvestigationsthatsupportdesignofthefacilities,
the waste package and performance models.
precise regulatory definitions are needed, the user should
consult the appropriate governing reference. 3.2.11 technical information—information available from
drawings, specifications, calculations, analyses, reactor opera-
3.2.1 disposal—the emplacement in a repository of high-
level radioactive waste, spent nuclear fuel, or other highly tional records, fabrication and construction records, other
design basis documents, regulatory or program requirements
radioactive material with no foreseeable intent of recovery,
whether or not such emplacement permits the recovery of such documents, or consensus codes and standards that describe
physical, performance, operational, or nuclear characteristics
waste.
3.2.2 engineered barrier system (EBS)—the waste packages or requirements.
and the underground facility, which means the underground 3.2.12 risk-informed—refers to an approach to the licensing
structure including openings and backfill materials. of a geologic repository based on the understanding that some
3.2.3 geologic repository—a system which is intended to be risk will always exist and that the engineered barrier system
used for, or may be used for, the disposal of radioactive wastes andnaturalbarriersystemaredesignedtoperformsuchthatthe
in excavated geologic media. A geologic repository includes risk is acceptable.
the geologic repository operations area, and the portion of the
3.2.13 risk-significant—pertaining to an engineered barrier
geologic setting that provides isolation of the radioactive system material that has been determined to have a significant
waste.
effect on the performance of the repository during the regula-
3.2.4 important to safety—refers to those engineered fea-
tory compliance period after closure.
tures of the geologic repository operations area whose function
3.2.14 boundary dose risk—the quantitative estimate of the
expected annual dose to an individual at the repository site
boundary over the compliance period weighted by the prob-
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
ability of occurrence. (10 CFR 63.113)
4th Floor, New York, NY 10036, http://www.ansi.org.
AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
3.3 Definitions of Terms Specific to This Standard:
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
3.3.1 The following definitions are defined only for the
www.access.gpo.gov.
usage in this standard, and for the explanation of the analyses
See Compilation of ASTM Standard Definitions, available from ASTM
Headquarters, 100 Barr Harbor Drive, West Conshohocken, PA 19428. contained herein.
C1174 − 07 (2013)
3.3.2 accelerated test—a test that results in an increase in simplifications, and/or idealizations) that describe the system
the rate of an alteration mode or in the extent of reaction or explain the phenomenon, often expressed mathematically.
progress, when compared with expected service conditions.
3.3.17 predict—declare in advance the behavior of a mate-
Changesintheexpectedalterationmechanism(s)causedbythe
rial on the basis of a model.
accelerated test conditions, if any, must be accounted for in the
3.3.18 mechanistic model—model derived from accepted
use of the accelerated test data.
fundamentallawsgoverningthebehaviorofmatterandenergy.
3.3.3 alteration—any change in the form, state, or proper-
Itcorrespondstooneendofaspectrumofmodelswithvarying
ties of a material.
degrees of empiricism.
3.3.4 alteration mechanism—the fundamental chemical or
3.3.19 pyrophoric—capable of igniting spontaneously un-
physical processes by which alteration occurs.
der temperature, chemical, or physical/mechanical conditions
specific to the storage, handling, or transportation environment
3.3.5 alteration mode—a particular form of alteration, for
example, dissolution or passivation.
3.3.20 semi-empirical model—a model based partially on a
mechanistic understanding and partially on empirical fits to
3.3.6 analog—a material, process, or system whose compo-
data from experiments.
sition and environmental history are sufficiently similar to that
3.3.21 service condition test—a test with a material that is
anticipated for the materials of interest to permit use of insight
conducted under conditions in which the values of the inde-
gained regarding its condition or behavior to be applied to a
pendent variables characterizing the service environment are
material, process, or system of interest.
within the range expected in actual service.
3.3.7 attribute test—a test conducted to provide material
3.3.22 model validation—the process through which model
properties that are required as input to behavior models, but
predictions are compared with independent measurements or
that are not themselves responses to the environment. Ex-
analyses to provide confidence that a model accurately predicts
amples are density, thermal conductivity, mechanical
the alteration behavior of waste package/EBS materials under
properties, radionuclide content of waste forms, etc.
particular sets of credible environmental conditions. This
3.3.8 behavior—the response of a material to the environ-
provides confidence in the capability of the model to predict
ment in which it is placed.
alteration behavior under conditions or durations that have not
3.3.9 bounding model—a model that yields values for de-
been tested directly.An alteration model that has been demon-
pendent variables or effects that are expected to be either
strated to provide bounding results under all credible environ-
always greater than or always less than those expected for the
mental conditions, and is used to provide bounding values for
variables or effects to be bounded.
the alteration behavior, may be regarded as validated for its
intended usage.
3.3.10 characterization test—in high-level radioactive
waste management, any test or analysis conducted principally
4. Summary of Practice
to furnish information used to determine parameter values for
4.1 This practice covers the general approach for proceed-
a model or develop a mechanistic understanding of alteration.
Examples include polarization tests, solubility measurements, ing from the statement of a problem in prediction of long-term
behavior of materials, through the development, validation,
etc.
and confirmation of appropriate models, to formulation of
3.3.11 confirmation test—a test in which results are not used
actual predictions.
in the initial development of a model or the determination of
parameter values for a model but are used for comparison with
5. Significance and Use
the predictions of that model for model validation.
5.1 This practice
...
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