ASTM C1431-99
(Guide)Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
SCOPE
1.1 This guide covers corrosion testing of aluminum-based spent nuclear fuel in support of geologic repository disposal (per the requirements in 10 CFR 60 and 40 CFR 191). The testing described in this document is designed to provide data for analysis of the chemical stability and radionuclide release behavior of aluminum-based waste forms produced from aluminum-based spent nuclear fuels. The data and analyses from the corrosion testing will support the technical basis for inclusion of aluminum-based spent nuclear fuels in the repository source term. Interim storage and transportation of the spent fuel will precede geologic disposal; therefore, reference is also made to the requirements for interim storage (per 10 CFR 72) and transportation (per 10 CFR 71). The analyses that will be based on the data developed are also necessary to support the safety analyses reports (SARs) and performance assessments (PAs) for disposal systems.
1.2 Spent nuclear fuel that is not reprocessed must be safely managed prior to transportation to, and disposal in, a geologic repository. Placement is an interim storage facility may include direct placement of the irradiated fuel or treatment of the fuel prior to placement, or both. The aluminum-based waste forms may be required to be ready for geologic disposal, or road ready, prior to placement in extended interim storage. Interim storage facilities, in the United States, handle fuel from civilian commercial power reactors, defense nuclear materials production reactors, and research reactors. The research reactors include both foreign and domestic reactors. The aluminum-based fuels in the spent fuel inventory in the United States are primarily from defense reactors and from foreign and domestic research reactors. The aluminum-based spent fuel inventory includes several different fuel forms and levels of 235U enrichment. Highly enriched fuels (235U enrichment leves > 20%) are part of this inventory.
1.3 Knowledge of the corrosion behavior of aluminum-based spent nuclear fuels is required to ensure safety and to support licensing or other approval activities, or both, necessary for disposal in a geologic repository. The response fo the aluminum-based spent nuclear fuel waste form(s) to disposal environments must be established for configuration-safety analyses, criticality analyses, PAs, and other analyses required to assess storage, treatment, transportation, and disposal of spent nuclear fuels. This is particularly important for the highly enriched, aluminum-based spent nuclear fuels. The test protocols described in this guide are designed to establish material response under the repository relevant conditions.
1.4 The majority of the aluminum-based spent nuclear fuels are aluminum clad, aluminum-uranium alloys. The aluminum-uranium alloy typically consists of uranium aluminide particles dispersed in an aluminum matrix. Other aluminum-based fuels include dispersions of uranium oxide, uranium silicide, or uranium carbide particles in an aluminum matrix. These particles, including the aluminides, are generally cathodic to the aluminum matrix. Selective leaching of the aluminum in the exposure environment may provide a mechanism for redistribution and relocation of the uranium-rich particles. Particle redistribution tendencies will depend on the nature of the aluminum corrosion processes and the size, shape, distribution and relative reactivity of the uranium-rich particles. Interpretation of test data will require an understanding of the material behavior. This understanding will enable evaluation of the design and configuration of the waste package to ensure that unfilled regions in the waste package do not provide sites for the relocation of the uranium-rich particles into nuclear critical configurations. Test samples must be evaluated, prior to testing, to ensure that the size and shape of the uranium-rich particles in the test samples are representative of the particles ...
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Designation:C1431–99
Standard Guide for
Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in
1
Support of Repository Disposal
This standard is issued under the fixed designation C 1431; 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 sary for disposal in a geologic repository. The response of the
aluminum-based spent nuclear fuel waste form(s) to disposal
1.1 This guide covers corrosion testing of aluminum-based
environments must be established for configuration-safety
spent nuclear fuel in support of geologic repository disposal
analyses, criticality analyses, PAs, and other analyses required
(per the requirements in 10 CFR 60 and 40CFR191). The
to assess storage, treatment, transportation, and disposal of
testing described in this document is designed to provide data
spentnuclearfuels.Thisisparticularlyimportantforthehighly
for analysis of the chemical stability and radionuclide release
enriched, aluminum-based spent nuclear fuels. The test proto-
behavior of aluminum-based waste forms produced from
cols described in this guide are designed to establish material
aluminum-based spent nuclear fuels. The data and analyses
response under the repository relevant conditions.
from the corrosion testing will support the technical basis for
1.4 The majority of the aluminum-based spent nuclear fuels
inclusion of aluminum-based spent nuclear fuels in the reposi-
are aluminum clad, aluminum-uranium alloys. The aluminum-
tory source term. Interim storage and transportation of the
uraniumalloytypicallyconsistsofuraniumaluminideparticles
spent fuel will precede geologic disposal; therefore, reference
dispersed in an aluminum matrix. Other aluminum-based fuels
is also made to the requirements for interim storage (per 10
include dispersions of uranium oxide, uranium silicide, or
CFR 72) and transportation (per 10 CFR 71).The analyses that
uranium carbide particles in an aluminum matrix. These
will be based on the data developed are also necessary to
particles, including the aluminides, are generally cathodic to
support the safety analyses reports (SARs) and performance
the aluminum matrix. Selective leaching of the aluminum in
assessments (PAs) for disposal systems.
the exposure environment may provide a mechanism for
1.2 Spent nuclear fuel that is not reprocessed must be safely
redistribution and relocation of the uranium-rich particles.
managed prior to transportation to, and disposal in, a geologic
Particle redistribution tendencies will depend on the nature of
repository. Placement is an interim storage facility may include
the aluminum corrosion processes and the size, shape, distri-
direct placement of the irradiated fuel or treatment of the fuel
bution and relative reactivity of the uranium-rich particles.
prior to placement, or both. The aluminum-based waste forms
Interpretation of test data will require an understanding of the
may be required to be ready for geologic disposal, or road
materialbehavior.Thisunderstandingwillenableevaluationof
ready, prior to placement in extended interim storage. Interim
the design and configuration of the waste package to ensure
storagefacilities,intheUnitedStates,handlefuelfromcivilian
that unfilled regions in the waste package do not provide sites
commercial power reactors, defense nuclear materials produc-
for the relocation of the uranium-rich particles into nuclear
tion reactors, and research reactors. The research reactors
critical configurations.Test samplesmust beevaluated, prior to
include both foreign and domestic reactors. The aluminum-
testing, to ensure that the size and shape of the uranium-rich
based fuels in the spent fuel inventory in the United States are
particles in the test samples are representative of the particles
primarily from defense reactors and from foreign and domestic
in the waste form being evaluated.
research reactors. The aluminum-based spent fuel inventory
235
1.5 The use of the data obtained by the testing described in
includes several different fuel forms and levels of U enrich-
235
this guide will be optimized to the extent the samples mimic
ment. Highly enriched fuels ( U enrichment levels > 20 %)
the condition of the waste form during actual repository
are part of this inventory.
exposure. The use of Practice C 1174 is recommended for
1.3 Knowledge of the corrosion behavior of aluminum-
guidance. The selection of test samples, which may be unaged
based spent nuclear fuels is required to ensure safety and to
or artificially aged, should ensure that the test samples and
support licensing or other approval activities, or both,
...
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