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ASTM C 1174 : 2020

Current
Current

The latest, up-to-date edition.

Standard Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
Available format(s)

Hardcopy , PDF

Language(s)

English

Published date

01-03-2020

1.1This 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.

1.2The 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.

1.3This 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.

1.3.1Steps 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.

1.3.2The 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.

1.3.3For the purpose of this guide, 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: attribute tests, characterization tests, accelerated tests, service condition tests, and confirmation tests.

1.4This guide does not address testing required to define or characterize the repository environment (that is, the groundwater quantity or chemistry, host rock properties, etc.). The logical approach and testing concepts described herein can be applied to the disposal system.

1.5This 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

1.6This 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.

Committee
C 26
DocumentType
Guide
Pages
23
ProductNote
This standard is also refers to CFR 10,Public Law 97-425,NUREG-1804,SKI 99-2,IAEA SSR-5,IAEA GSG-3,SSMFS 2008-37,Finland Government Decree (736/2008).
PublisherName
American Society for Testing and Materials
Status
Current
Supersedes

ASTM C 1682 : 2017 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
ASTM C 1285 : 2014 Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)
ASTM C 1220 : 2017 Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste
ASTM C 1431 : 1999 : R2018 Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
ASTM E 2891 : 2013 Standard Guide for Multivariate Data Analysis in Pharmaceutical Development and Manufacturing Applications
ASTM C 1553 : 2016 Standard Guide for Drying Behavior of Spent Nuclear Fuel

ASTM E 177 : 1990 : REV A : R1996 Standard Practice for Use of the Terms Precision and Bias in ASTM Test Methods
ASTM C 859 : 2023 Standard Terminology Relating to Nuclear Materials
ASTM C 859 : 2014 : REV B Standard Terminology Relating to Nuclear Materials
ASTM C 859 : 2024 Standard Terminology Relating to Nuclear Materials
ASTM E 178 : 2016 : REV A Standard Practice for Dealing With Outlying Observations
ASTM C 1285 : 2021 Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)
ASTM E 178 : 2021 Standard Practice for Dealing With Outlying Observations
ASTM E 583 : 1987 Practice for Systematizing the Development of (ASTM) Voluntary Consensus Standards for the Solution of Nuclear and Other Complex Problems (Withdrawn 1995)
ASTM E 178 : 2000 Standard Practice for Dealing With Outlying Observations
ASTM E 178 : 1994 Standard Practice for Dealing With Outlying Observations
ASTM C 859 : 2022 Standard Terminology Relating to Nuclear Materials
ASTM C 859 : 2022 : REV A Standard Terminology Relating to Nuclear Materials

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