ASTM C1174-04

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

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 judgement, interpretation of data obtained 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 for model development and use. These tests may include but are not limited to the following:
Attribute tests to measure intrinsic materials properties,
Characterization tests to measure the effects of material and environmental variables on behavior,
Accelerated tests to accelerate alteration and determine important mechanisms and processes that can affect the lifetime licensed performance of waste form and EBS materials,
Service condition tests to confirm the appropriateness of the model and variables for anticipated disposal conditions,
Confirmation tests to verify the predictive capacity of the model, and
Tests or analyses performed with analog materials to identify important mechanisms, verify the appropriateness of an accelerated test method, and to confirm long-term model predictions.
1.2 The purpose of this practice is to provide methods for developing models that can be used for the prediction of materials behavior over the long periods of time pertinent to the service life of a geologic repository as part of the basis for performance assessment of the repository.
1.3 This practice also addresses uncertainties in materials behavior models and their impact on the confidence in the performance assessment.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

General Information

• Status: Historical
• Publication Date: 31-May-2004
• ICS: 13.030.30 - Special wastes
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.13 - Spent Fuel and High Level Waste

Relations

• Replaces: ASTM C1174-97 - Standard Practice for Prediction of the Long-Term Behavior of Waste Package Materials Including Waste Forms Used in the Geologic Disposal of High-Level Nuclear Waste
• Effective Date: 01-Jun-2004
• Replaced By: ASTM C1174-07 - 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
• Effective Date: 01-Jun-2007
• Referred By: ASTM C1562-10(2018) - Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1553-21 - Standard Guide for Drying of Spent Nuclear Fuel
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1220-21 - Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1662-18 - Standard Practice for Measurement of the Glass Dissolution Rate Using the Single-Pass Flow-Through Test Method
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1285-21 - Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1926-23 - Standard Test Method for Measurement of Glass Dissolution Rate Using Stirred Dilute Reactor Conditions on Monolithic Samples
• Effective Date: 01-Jun-2004
• Referred By: ASTM E2891-20 - Standard Guide for Multivariate Data Analysis in Pharmaceutical Development and Manufacturing Applications
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1431-99(2018) - Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1682-21 - Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
• Effective Date: 01-Jun-2004

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:C1174–04
Standard Practice for
Prediction of the Long-Term Behavior of Materials, Including
Waste Forms, Used in Engineered Barrier Systems (EBS) for
1
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
2
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,
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear contact ASTM Customer Service at [e-mail]. 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.
3
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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