ASTM C1682-17
(Guide)Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
SIGNIFICANCE AND USE
5.1 In order to demonstrate conformance to regulatory requirements and support the post-closure repository performance assessment information is required about the attributes, characteristics, and behavior of the SNF. These properties of the SNF in turn support the transport, interim storage, and repository pre-closure safety analyses, and repository post-closure performance assessment. In the United States, the interim dry storage of commercial LWR SNF is regulated per the Code of Federal Regulations, Title 10, Part 72, which requires that the cladding must not sustain during the interim storage period any “gross” damage sufficient to release fuel from the cladding into the container environment. In other countries, the appropriate governing body will set regulations regarding interim dry storage of commercial LWR SNF. However, cladding damage insufficient to allow the release of fuel during the interim storage period may still occur in the form of small cracks or pinholes. These cracks/pinholes could be sufficient to classify the fuel as “ failed fuel” or “breached fuel” per the definitions given in Section 3 for repository disposal purposes, because they could allow contact of water vapor or liquid with the spent fuel matrix and thus provide a pathway for radionuclide release from the waste form. Also, pinholes/cracks in fuel rods in dry or wet interim storage can also develop into much larger defects (for example, the phenomenon of cladding “unzipping”) under long-term repository conditions. Therefore SNF characterization should be adequate to determine the amount of “failed fuel” for either usage as required. This could involve the examination of reactor operating records, ultrasonic testing, sipping, and analysis of the residual water and drying kinetics of the spent fuel assemblies or canisters.
5.2 Regulations in each country may contain constraints and limitations on the chemical or physical (or both) properties and long-term degradation behavior of the ...
SCOPE
1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors and mixed oxide (MOX) spent fuel. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF.
1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product content, and such environmental response characteristics as drying rates, oxidation rates (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/degradation rates. Not all of the characterization tests described herein must necessarily be performed for any given analysis of SNF performance for interim storage, transportation, or geological repository disposal, particularly in areas where an extensive body of literature already exists for the parameter of interest in the specific service condition.
1.3 It is assumed in formulating the SNF characterization activities in this guide that the SNF has been stored in an interim storage facility at some time between reactor discharge and dry transport to a repository. The SNF may have been stored either wet (for example, a spent fuel pool), or dry (for example, an independent spent fuel storage installation (IS...
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Designation: C1682 − 17
Standard Guide for
Characterization of Spent Nuclear Fuel in Support of Interim
1
Storage, Transportation and Geologic Repository Disposal
This standard is issued under the fixed designation C1682; 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 1.4 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
1.1 This guide provides guidance for the types and extent of
standard.
testing that would be involved in characterizing the physical
and chemical nature of spent nuclear fuel (SNF) in support of 1.5 This standard does not purport to address all of the
its interim storage, transport, and disposal in a geologic safety concerns, if any, associated with its use. It is the
repository. This guide applies primarily to commercial light responsibility of the user of this standard to establish appro-
water reactor (LWR) spent fuel and spent fuel from weapons priate safety and health practices and determine the applica-
production, although the individual tests/analyses may be used bility of regulatory limitations prior to use.
as applicable to other spent fuels such as those from research
1.6 This international standard was developed in accor-
and test reactors and mixed oxide (MOX) spent fuel. The
dance with internationally recognized principles on standard-
testing is designed to provide information that supports the
ization established in the Decision on Principles for the
design, safety analysis, and performance assessment of a
Development of International Standards, Guides and Recom-
geologic repository for the ultimate disposal of the SNF.
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
1.2 The testing described includes characterization of such
physical attributes as physical appearance, weight, density,
2. Referenced Documents
shape/geometry, degree, and type of SNF cladding damage.
2
The testing described also includes the measurement/
2.1 ASTM Standards:
examination of such chemical attributes as radionuclide
C170/C170M Test Method for Compressive Strength of
content, microstructure, and corrosion product content, and
Dimension Stone
such environmental response characteristics as drying rates,
C696 Test Methods for Chemical, Mass Spectrometric, and
oxidation rates (in dry air, water vapor, and liquid water),
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
ignition temperature, and dissolution/degradation rates. Not all
oxide Powders and Pellets
of the characterization tests described herein must necessarily
C698 Test Methods for Chemical, Mass Spectrometric, and
be performed for any given analysis of SNF performance for
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
interim storage, transportation, or geological repository
ides ((U, Pu)O )
2
disposal, particularly in areas where an extensive body of
C859 Terminology Relating to Nuclear Materials
literature already exists for the parameter of interest in the
C1174 Practice for Prediction of the Long-Term Behavior of
specific service condition.
Materials, Including Waste Forms, Used in Engineered
Barrier Systems (EBS) for Geological Disposal of High-
1.3 It is assumed in formulating the SNF characterization
Level Radioactive Waste
activities in this guide that the SNF has been stored in an
C1380 Test Method for the Determination of Uranium Con-
interim storage facility at some time between reactor discharge
tent and Isotopic Composition by Isotope Dilution Mass
and dry transport to a repository. The SNF may have been
Spectrometry
stored either wet (for example, a spent fuel pool), or dry (for
C1413 Test Method for Isotopic Analysis of Hydrolyzed
example, an independent spent fuel storage installation
Uranium Hexafluoride and Uranyl Nitrate Solutions by
(ISFSI)), or both, and that the manner of interim storage may
Thermal Ionization Mass Spectrometry
affect the SNF characteristics.
C1454 Guide for Pyrophoricity/Combustibility Testing in
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 July 1, 2017. Published August 2017. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 2009. Last previous edition approved in 2009 as C1682 – 09. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1682-17. the ASTM web
...
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: C1682 − 09 C1682 − 17
Standard Guide for
Characterization of Spent Nuclear Fuel in Support of Interim
1
Storage, Transportation and Geologic Repository Disposal
This standard is issued under the fixed designation C1682; 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 guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and
chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This
guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the
individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. reactors and
mixed oxide (MOX) spent fuel. The testing is designed to provide information that supports the design, safety analysis, and
performance assessment of a geologic repository for the ultimate disposal of the SNF.
1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density,
shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of
such chemical attributes as radionuclide content, microstructure, and corrosion product content, and such environmental response
characteristics as drying rates, oxidation rates (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/
degradation rates. Not all of the characterization tests described herein must necessarily be performed for any given analysis of
SNF repository performance,performance for interim storage, transportation, or geological repository disposal, particularly in areas
where an extensive body of literature already exists for the parameter of interest.interest in the specific service condition.
1.3 It is assumed in formulating the SNF characterization activities in this guide that the SNF has been stored in an interim
storage facility at some time between reactor discharge and dry transport to the geologic a repository. The SNF may have been
stored either wet (for example, a spent fuel pool), or dry (for example, an independent spent fuel storage installation (ISFSI)), or
both, and that the manner of interim storage may affect the SNF characteristics.
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.5 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
limitations prior to use.
1.6 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:
C170/C170M Test Method for Compressive Strength of Dimension Stone
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
C698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U,
Pu)O )
2
C859 Terminology Relating to Nuclear Materials
1
This guide 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 June 1, 2009July 1, 2017. Published July 2009August 2017. Originally approved in 2009. Last previous edition approved in 2009 as C1682 – 09.
DOI: 10.1520/C1682-09.10.1520/C1682-17.
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 States
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