ASTM C1174-20
(Guide)Standard Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
Standard Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
SIGNIFICANCE AND USE
5.1 This guide supports the development of material behavior models that can be used to estimate performance of the EBS materials during the post-closure period of a high-level nuclear waste repository for times much longer than can be tested directly. This guide is intended for modeling the degradation behaviors of materials proposed for use in an EBS designed to contain radionuclides over tens of thousands of years and more. There is both national and international recognition of the importance of the use and long-term performance of engineered materials in geologic repository design. Use of the models developed following the approaches described in this guide is intended to address established regulations, such as:
5.1.1 U.S. 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. These barriers include engineered barriers designed to prevent the migration of radionuclides out of the engineered system, and the geologic host medium that provides an additional transport barrier between the engineered system and biosphere. The regulations of the U.S. Nuclear Regulatory Commission for geologic disposal require a performance confirmation program to provide data through tests and analyses, where practicable, that demonstrate engineered systems and components that are designed or assumed to act as barriers after permanent closure are functioning as intended and anticipated.
5.1.2 IAEA Safety Requirements specify that engineered barriers shall be designed and the host environment shall be selected to provide containment of the radionuclides associated with the wastes.
5.1.3 The Swedish Regulatory Authority has provided general advice to the repository developer that the application of best available technique be followed in connection with disposal, which means that the siting, design, construction, and operation of the repository and appurtenant syste...
SCOPE
1.1 This guide addresses how various test methods and data analyses can be used to develop models for the evaluation of the long-term alteration behavior of materials used in an engineered barrier system (EBS) for the disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste forms and EBS materials is important because it affects the retention of radionuclides within the disposal system either directly, as in the case of waste forms in which the radionuclides are initially immobilized, or indirectly, as in the case of EBS containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms degrade.
1.2 The purpose of this guide is to provide a scientifically-based strategy for developing models that can be used to estimate material alteration behavior after a repository is permanently closed (that is, in the post-closure period). Because the timescale involved with geological disposal precludes direct validation of predictions, mechanistic understanding of the processes based on detailed data and models and consideration of the range of uncertainty are recommended.
1.3 This guide addresses the scientific bases and uncertainties in material behavior models and the impact on the confidence in the EBS design criteria and repository performance assessments using those models. This includes the identification and use of conservative assumptions to address uncertainty in the long-term performance of materials.
1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials include problem definition, laboratory and field testing, modeling of individual and coupled processes, and model confirmation.
1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations, expert judgments, and interpretations of d...
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This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: C1174 − 20
Standard Guide for
Evaluation of Long-Term Behavior of Materials Used in
Engineered Barrier Systems (EBS) for Geological Disposal
1
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 considerations, expert judgments, and interpretations of data
obtained from tests and analyses of appropriate analogs.
1.1 This guide addresses how various test methods and data
1.3.3 For the purpose of this guide, tests are categorized
analyses can be used to develop models for the evaluation of
according to the information they provide and how it is used
the long-term alteration behavior of materials used in an
for model development, support, and use. These tests may
engineered barrier system (EBS) for the disposal of spent
include but are not limited to: attribute tests, characterization
nuclear fuel (SNF) and other high-level nuclear waste in a
tests, accelerated tests, service condition tests, and confirma-
geologicrepository.Thealterationbehaviorofwasteformsand
tion tests.
EBS materials is important because it affects the retention of
radionuclides within the disposal system either directly, as in 1.4 This guide does not address testing required to define or
characterize the repository environment (that is, the ground-
the case of waste forms in which the radionuclides are initially
immobilized, or indirectly, as in the case of EBS containment water quantity or chemistry, host rock properties, etc.). The
logical approach and testing concepts described herein can be
materials that restrict the ingress of groundwater or the egress
of radionuclides that are released as the waste forms degrade. applied to the disposal system.
1.5 This standard does not purport to address all of the
1.2 The purpose of this guide is to provide a scientifically-
safety concerns, if any, associated with its use. It is the
based strategy for developing models that can be used to
responsibility of the user of this standard to establish appro-
estimate material alteration behavior after a repository is
priate safety, health, and environmental practices and deter-
permanently closed (that is, in the post-closure period). Be-
mine the applicability of regulatory limitations prior to use.
cause the timescale involved with geological disposal pre-
1.6 This international standard was developed in accor-
cludesdirectvalidationofpredictions,mechanisticunderstand-
dance with internationally recognized principles on standard-
ing of the processes based on detailed data and models and
ization established in the Decision on Principles for the
consideration of the range of uncertainty are recommended.
Development of International Standards, Guides and Recom-
1.3 This guide addresses the scientific bases and uncertain-
mendations issued by the World Trade Organization Technical
ties in material behavior models and the impact on the
Barriers to Trade (TBT) Committee.
confidence in the EBS design criteria and repository perfor-
mance assessments using those models. This includes the
2. Referenced Documents
identification and use of conservative assumptions to address
2
2.1 ASTM Standards:
uncertainty in the long-term performance of materials.
C859 Terminology Relating to Nuclear Materials
1.3.1 Steps involved in evaluating the performance of waste
C1285 Test Methods for Determining Chemical Durability
forms and EBS materials include problem definition, labora-
of Nuclear, Hazardous, and Mixed Waste Glasses and
tory and field testing, modeling of individual and coupled
MultiphaseGlassCeramics:TheProductConsistencyTest
processes, and model confirmation.
(PCT)
1.3.2 The estimates of waste form and EBS material perfor-
C1663 Test Method for Measuring Waste Glass or Glass
mance are based on models derived from theoretical
Ceramic Durability by Vapor Hydration Test
E177 Practice for Use of the Terms Precision and Bias in
ASTM Test Methods
1
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
2
High Level Waste. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Feb. 15, 2020. Published March 2020. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1991. Last previous edition approved in 2017 as C1174 – 17.
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: C1174 − 17 C1174 − 20
Standard PracticeGuide for
Evaluation of the Long-Term Behavior of Materials Used in
Engineered Barrier Systems (EBS) for Geological Disposal
1
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 This practice addresses how various test methods and data analyses can be used to develop models for the evaluation of the
long-term alteration behavior of materials used in engineered barrier system (EBS) for the disposal of spent nuclear fuel (SNF)
and other high-level nuclear waste in a geologic repository. The alteration behavior of waste forms and EBS materials is important
because it affects the retention of radionuclides within the disposal system either directly, as in the case of waste forms in which
the radionuclides are initially immobilized, or indirectly, as in the case of EBS containment materials that restrict the ingress of
groundwater or the egress of radionuclides that are released as the waste forms degrade.
1.2 The purpose of this practice is to provide a scientifically-based strategy for developing models that can be used to estimate
material alteration behavior after a repository is permanently closed (that is, the post-closure period) because the timescales
involved with geological disposal preclude direct validation of predictions.
1.3 This practice also addresses uncertainties in materials behavior models and the impact on the confidence in the EBS design
criteria, the scientific bases of alteration models, and repository performance assessments using those models. This includes the
identification and use of conservative assumptions to address uncertainty in the long-term performance of materials.
1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials include problem definition, laboratory and
field testing, modeling of individual and coupled processes, and model confirmation.
1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations,
expert judgments, and interpretations of data obtained from tests and analyses of appropriate analogs.
1.3.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used for
model development, support, and use. These tests may include but are not limited to: accelerated tests, attribute tests,
characterization tests, confirmation tests, and service condition tests.
1.4 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.
1.5 This international standard was developed in accordance with internationally recognized principles on standardization
established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued
by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
2. Referenced Documents
2
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C1285 Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase
Glass Ceramics: The Product Consistency Test (PCT)
C1682 Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository
Disposal
1
This practiceguide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
High Level Waste.
Current edition approved July 1, 2017Feb. 15, 2020. Published August 2017March 2020. Originally approved in 1991. Last previous edition approved in 20132017 as
C1174 – 07 (2013).C1174 – 17. DOI: 10.1520/C1174-17.10.1520/C1174-20.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United St
...
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