ASTM C1682-09
(Guide)Standard Guide for Characterization of Spent Nuclear Fuel in Support of Geologic Repository Disposal
Standard Guide for Characterization of Spent Nuclear Fuel in Support of Geologic Repository Disposal
SIGNIFICANCE AND USE
In order to demonstrate conformance to regulatory requirements and support the postclosure repository performance assessment information is required about the attributes, characteristics, and behavior of the SNF need to be determined. These properties of the SNF in turn support the transport, interim storage, and repository preclosure safety analyses, and repository postclosure performance assessment. The interim dry storage of commercial LWR SNF is regulated per 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. 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.
In the U.S. the disposal of spent nuclear fuel (SNF) and high level waste (HLW) in a geologic repository is regulated under the Code of Federal Regulations, Title 10, Part 60 (which pertains to any geologic repository built in the U.S.), Code of Federal Regulations, Title 10, Part 63 (which pertains...
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. 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, particularly in areas where an extensive body of literature already exists for the parameter of interest.
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 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 ...
General Information
Relations
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: C1682 − 09
Standard Guide for
Characterization of Spent Nuclear Fuel in Support of
1
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
safety concerns, if any, associated with its use. It is the
its interim storage, transport, and disposal in a geologic
responsibility of the user of this standard to establish appro-
repository. This guide applies primarily to commercial light
priate safety and health practices and determine the applica-
water reactor (LWR) spent fuel and spent fuel from weapons
bility of regulatory limitations prior to use.
production, although the individual tests/analyses may be used
as applicable to other spent fuels such as those from research
2. Referenced Documents
and test reactors. The testing is designed to provide informa-
tion that supports the design, safety analysis, and performance 2
2.1 ASTM Standards:
assessment of a geologic repository for the ultimate disposal of
C170/C170M Test Method for Compressive Strength of
the SNF.
Dimension Stone
C696 Test Methods for Chemical, Mass Spectrometric, and
1.2 The testing described includes characterization of such
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
physical attributes as physical appearance, weight, density,
oxide Powders and Pellets
shape/geometry, degree, and type of SNF cladding damage.
C698 Test Methods for Chemical, Mass Spectrometric, and
The testing described also includes the measurement/
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
examination of such chemical attributes as radionuclide
ides ((U, Pu)O )
2
content, microstructure, and corrosion product content, and
C859 Terminology Relating to Nuclear Materials
such environmental response characteristics as drying rates,
C1174 Practice for Prediction of the Long-Term Behavior of
oxidation rates (in dry air, water vapor, and liquid water),
Materials, Including Waste Forms, Used in Engineered
ignition temperature, and dissolution/degradation rates. Not all
Barrier Systems (EBS) for Geological Disposal of High-
of the characterization tests described herein must necessarily
Level Radioactive Waste
be performed for any given analysis of SNF repository
C1380 Test Method for the Determination of Uranium Con-
performance, particularly in areas where an extensive body of
tent and Isotopic Composition by Isotope Dilution Mass
literature already exists for the parameter of interest.
Spectrometry
1.3 It is assumed in formulating the SNF characterization C1413 Test Method for Isotopic Analysis of Hydrolyzed
Uranium Hexafluoride and Uranyl Nitrate Solutions by
activities in this guide that the SNF has been stored in an
Thermal Ionization Mass Spectrometry
interim storage facility at some time between reactor discharge
C1454 Guide for Pyrophoricity/Combustibility Testing in
anddrytransporttothegeologicrepository.TheSNFmayhave
Support of Pyrophoricity Analyses of Metallic Uranium
been stored either wet (for example, a spent fuel pool), or dry
Spent Nuclear Fuel
(for example, an independent spent fuel storage installation
C1553 Guide for Drying Behavior of Spent Nuclear Fuel
(ISFSI)), or both, and that the manner of interim storage may
E170 Terminology Relating to Radiation Measurements and
affect the SNF characteristics.
Dosimetry
1
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
2
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and For referenced ASTM standards, visit the ASTM website, www.astm.org, or
High Level Waste. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Current edition approved June 1, 2009. Published July 2009. DOI: 10.1520/ Standards volume information, refer to the standard’s Document Summary page on
C1682-09. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1682 − 09
3
2.2 U.S. Government Documents Part 72, Section 122(h)). It is not expected that minor cladding
Code of Federal Regulations, Title 10, Part 60 Disposal of defects such as pinhole cracks
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.