ASTM C1174-04

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Designation:C1174–04
Standard Practice for
Prediction of the Long-Term Behavior of Materials, Including
Waste Forms, Used in Engineered Barrier Systems (EBS) for
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Geological Disposal of High-Level Radioactive Waste
This standard is issued under the fixed designation C 1174; 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 (e) 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
1.2 The purpose of this practice is to provide methods for
a geologic repository. The alteration behavior of waste form
developing models that can be used for the prediction of
and EBS materials is important because it affects the retention
materials behavior over the long periods of time pertinent to
of radionuclides by the disposal system. The waste form and
the service life of a geologic repository as part of the basis for
EBS materials provide a barrier to release either directly (as in
performance assessment of the repository.
the case of waste forms in which the radionuclides are initially
1.3 This practice also addresses uncertainties in materials
immobilized), or indirectly (as in the case of containment
behavior models and their impact on the confidence in the
materials that restrict the ingress of groundwater or the egress
performance assessment.
of radionuclides that are released as the waste forms and EBS
1.4 This standard does not purport to address all of the
materials degrade).
safety concerns, if any, associated with its use. It is the
1.1.1 Steps involved in making such predictions include
responsibility of the user of this standard to establish appro-
problem definition, testing, modeling, and model confirmation.
priate safety and health practices and determine the applica-
1.1.2 The predictions are based on models derived from
bility of regulatory requirements prior to use.
theoretical considerations, expert judgement, interpretation of
data obtained from tests, and appropriate analogs.
2. Referenced Documents
1.1.3 For the purpose of this practice, tests are categorized
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2.1 ASTM Standards:
according to the information they provide and how it is used
C 1285 Test Methods for Determining Chemical Durability
for model development and use. These tests may include but
of Nuclear, Hazardous, and Mixed Waste Glasses: The
are not limited to the following:
Product Consistency Test (PCT)
1.1.3.1 Attribute tests to measure intrinsic materials proper-
E 177 Practice for Use of the Terms Precision and Bias in
ties,
ASTM Test Methods
1.1.3.2 Characterization tests to measure the effects of
E 178 Practice for Dealing with Outlying Observations
material and environmental variables on behavior,
E 583 Practice for Systematizing the Development of
1.1.3.3 Accelerated tests to accelerate alteration and deter-
(ASTM) Voluntary Consensus Standards for the Solution
mine important mechanisms and processes that can affect the
of Nuclear and Other Complex Problems
lifetime licensed performance of waste form and EBS materi-
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2.2 ANSI Standard:
als,
ANSI/ASME NQA-1 Quality Assurance Program Require-
1.1.3.4 Service condition tests to confirm the appropriate-
ments for Nuclear Facility Applications
ness of the model and variables for anticipated disposal
conditions,
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For referenced ASTM standards, visit the ASTM website, www.astm.org, or
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This practice is under the jurisdiction of ASTM Committee C26 on Nuclear contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Repository Standards volume information, refer to the standard’s Document Summary page on
Waste Package Materials Testing. the ASTM website.
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CurrenteditionapprovedJune1,2004.PublishedJuly2004.Originallyapproved Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
in 1991. Last previous edition approved in 1997 as C 1174 – 97. 4th Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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