ASTM C1174-97
(Practice)Standard Practice for Prediction of the Long-Term Behavior of Waste Package Materials Including Waste Forms Used in the Geologic Disposal of High-Level Nuclear Waste
Standard Practice for Prediction of the Long-Term Behavior of Waste Package Materials Including Waste Forms Used in the Geologic Disposal of High-Level Nuclear Waste
SCOPE
1.1 This practice covers steps for the development of methods to aid in the prediction of the long-term behavior of waste package materials and waste forms used in the geologic disposal of high-level nuclear waste.
1.1.1 These steps include problem definition, testing, and modelling.
1.1.2 The predictions will be based on models derived from interpretation of data obtained from tests and appropriate analogs.
1.1.3 These tests may include but are not limited to the following:
1.1.3.1 Attribute tests,
1.1.3.2 Characterization tests,
1.1.3.3 Accelerated tests,
1.1.3.4 Service condition tests,
1.1.3.5 Analog tests, and
1.1.3.6 Confirmation tests.
1.2 The purpose of this practice is to provide information to serve as part of the basis for performance assessment of a geologic repository.
1.3 This practice does not cover other methods of making predictions such as use of peer judgments.
1.4 This standard does not purport to address the safety problems 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.
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Designation: C 1174 – 97
Standard Practice for
Prediction of the Long-Term Behavior of Materials, Including
Waste Forms, Used in Engineered Barrier Systems (EBS) for
Geological Disposal of High-Level Radioactive Waste
This standard is issued under the fixed designation C 1174; 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 E 177 Practice for Use of the Terms Precision and Bias in
ASTM Test Methods
1.1 This practice covers steps for the development of
E 178 Practice for Dealing with Outlying Observations
methods to aid in the prediction of the long-term behavior of
E 583 Practice for Systematizing the Development of
materials, such as “engineered barrier” system (EBS) materials
(ASTM) Voluntary Consensus Standards for the Solution
and waste forms, used in the geologic disposal of high-level
of Nuclear and Other Complex Problems
nuclear waste in the U.S. Government disposal site.
2.2 ANSI Standard:
1.1.1 These steps include problem definition, testing, mod-
ANSI Nuclear Quality Assurance for Waste Management
eling, and confirmation.
ANSI/ASME NQR-1 Quality Assurance Program Require-
1.1.2 The predictions are based on models derived from
ments for Nuclear Facilities
interpretation of data obtained from tests and appropriate
2.3 U.S. Government Documents:
analogs.
DOE/RW-0333P, Rev. 7, Quality Assurance Requirements
1.1.3 These tests may include but are not limited to the
and Description, USDOE OCRWM, Oct. 1995
following:
Code of Federal Regulations, Title 10, Part 60, Disposal of
1.1.3.1 Attribute tests,
High-Level Radioactive Wastes in Geologic Repositories,
1.1.3.2 Characterization tests,
U.S. Nuclear Regulatory Commission, January 1997
1.1.3.3 Accelerated tests,
Code of Federal Regulations Title 40, Part 191, Environ-
1.1.3.4 Service condition tests,
mental Radiation Protection Standards for Management
1.1.3.5 Analog tests, and
and Disposal of Spent Nuclear Fuel, High-Level and
1.1.3.6 Confirmation tests.
Transuranic Radioactive Wastes
1.1.4 Tests performed on analog materials.
Materials Characterization Center Guidelines for Accuracy
1.2 The purpose of this practice is to provide information to
and Precision of Test Data. In Nuclear Waste Materials
serve as part of the basis for performance assessment of a
Handbook-Volume on Test Methods. U.S. Department of
geologic repository.
Energy, DOE/TIC-11400
1.3 This practice does not cover other methods of making
Public Law 97-425, Nuclear Waste Policy Act of 1982, as
predictions such as use of expert judgment.
amended
1.4 This standard does not purport to address all of the
NUREG–0856, Final Technical Position on Documentation
safety concerns, if any, associated with its use. It is the
of Computer Codes for High–Level Waste Management
responsibility of the user of this standard to establish appro-
(1983)
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use.
Annual Book of ASTM Standards, Vol 14.02.
2. Referenced Documents
Annual Book of ASTM Standards, Vol 12.02.
4 th
2.1 ASTM Standards:
Available from American National Standards Institute, 11 W. 42nd St., 13
Floor, New York, NY 10036.
Available from Superintendent of Documents, U.S. Government Printing
This practice is under the jurisdiction of ASTM Committee C–26 on Nuclear Office, Washington, DC 20402.
Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Repository Available from the National Technical Information Service, U.S. Department of
Waste Package Materials Testing. Commerce, Springfield, VA 22161.
Current edition approved December 10, 1997. Published August 1998. Previ- In “United States Statutes at Large,” available from Superintendent of
ously published as C 1174 – 91. Last previous edition C 1174 – 91. Documents, U.S. Government Printing Office, Washington, DC 20002.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 1174
3. Terminology interest to permit use of conclusions about it to be applied to
the materials of interest. Alternatively, a process that is similar
3.1 Definitions:
enough to the process of interest to be used in this manner.
3.1.1 Definitions used in this practice are existing ASTM
3.2.6 attribute test—a test conducted to provide material
definitions, when applicable.
properties that are required as input to behavior models, but
3.1.1.1 Definitions of some terms “specific to this practice”
that are not themselves responses to the repository environ-
are based on the referenced Code of Federal Regulations, 10
ment. Examples are thermal conductivity, mechanical proper-
CFR Part 60, which is pertinent to this Standard and is under
ties, radionuclide content of waste forms, etc.
jurisdiction of the Nuclear Regulatory Commission (NRC). If
3.2.7 behavior—the response of a material to the environ-
precise regulatory definitions are needed, the user should
ment in which it is placed.
consult the appropriate governing reference.
3.2.8 bounding model—a model that yields values for
3.1.1.2 For any other use of the terms in this practice
dependent variables or effects that are expected to be either
consider carefully the context in which they are defined here.
always greater than or always less than those expected for the
3.1.2 Regulatory and Other Published Definitions:
variables or effects to be bounded.
3.1.2.1 disposal—the emplacement in a repository of high-
3.2.9 characterization test—in high-level radioactive waste
level radioactive waste, spent nuclear fuel, or other highly
management, any test conducted principally to furnish infor-
radioactive material with no foreseeable intent of recovery,
mation for a mechanistic understanding of alteration. Examples
whether or not such emplacement permits the recovery of such
include polarization tests, potential-pH (Pourbaix) diagrams,
waste.
solubility analyses, and x-ray diffraction of corrosion layers.
3.1.2.2 engineered barrier system (EBS)—the waste pack-
3.2.10 confirmation test—a test whose results had not been
ages and the underground facility, which means the under-
used in the validation of a model but are available and used
ground structure including openings and backfill materials.
later to further validate its predictions. Under current regula-
3.1.2.3 Geologic repository—a system which is intended to
tions, these tests can be conducted over much longer periods of
be used for, or may used for, the disposal of radioactive wastes
time than that available (in the pre-licensing phase of the
in excavated geologic media. A geologic repository includes:“
process) for validation tests.
(1) The geologic repository operations area, and (2) the portion
of the geologic setting that provides isolation of the radioactive 3.2.11 degradation—any change in the properties of a
material that adversely affects the behavior of that material;
waste.
3.1.2.4 high-level radioactive waste—includes spent adverse alteration.
3.2.12 empirical model—a model based only on observa-
nuclear fuel and solid wastes obtained on conversion of wastes
resulting from the reprocessing of spent nuclear fuel and other tions or data from experiments, without regard to mechanism
or theory.
wastes as approved by the NRC for disposal in a deep geologic
repository. 3.2.13 in-situ test—a test conducted in the geologic envi-
3.1.2.5 waste form—the radioactive waste materials and any ronment in which a material or waste form will be emplaced.
encapsulating or stabilizing matrix in which it is incorporated.
3.2.14 model—a simplified representation of a system or
3.1.2.6 waste package—the waste form and any containers,
phenomenon, along with any hypotheses required to describe
shielding, packing and other absorbent materials immediately
the system or explain the phenomenon, often mathematically.
surrounding an individual waste container.
3.2.15 predict—declare in advance the behavior of a mate-
3.2 Definitions of Terms Specific to This Standard:
rial on the basis of a model.
3.2.1 accelerated test—a test that results in an increase in
3.2.16 mechanistic model—model derived from accepted
the rate of an alteration mode, when compared with the rates
fundamental laws governing the behavior of matter and energy.
for service conditions. Changes in alteration mechanism, if
It corresponds to one end of a spectrum of models with varying
any, must be accounted for in the use of the accelerated test
degrees of empiricism.
data.
3.2.17 semi-empirical model—a model based partially on
3.2.2 alteration—any change in the form, state, or proper-
one or more mechanisms and partially on data from experi-
ties of a material.
ments.
3.2.3 alteration mechanism—the fundamental chemical or
3.2.18 service condition test—a test, of a material, con-
physical processes by which alteration occurs.
ducted under conditions in which the values of the independent
3.2.4 alteration mode—a particular form of alteration, for
variables characterizing the service environment are in the
example, general corrosion, passivation.
range expected in actual service.
3.2.5 analog—a material whose composition, and environ-
3.2.19 model validation—the process through which inde-
mental history are similar enough to those of the materials of
pendent measurements are used to ensure that a model accu-
rately predicts an alteration behavior of waste-package mate-
rials under a given set of environmental conditions (e.g. under
repository environment over the time periods required).
See Compilation of ASTM Standard Definitions, available from ASTM Head-
quarters, 100 Barr Harbor Drive, West Conshohocken, PA 19428.
An alternate to this practice’s recommendation (to demonstrate one or more
4. Summary of Practice
alteration mechanisms that apply to a behavior model) is the development of
4.1 This practice covers the general approach for proceed-
predictions based on the long–term approach to thermodynamic equilibrium (or
steady-state) behavior. ing from the statement of a problem in prediction of long-term
C 1174
behavior of materials, through the development and validation 5.5 The EBS environment of interest is that defined by the
of appropriate models, to formulation and confirmation of natural conditions (e.g. minerals, moisture, biota, and stresses)
actual predictions. as modified by effects of time and repository construction, and
operations, and the consequences of the radionuclide decay,
5. Significance and Use
e.g. radiation, heat. The conditions associated with both antici-
5.1 This practice is intended to guide in making predictions
pated and unanticipated scenarios are to be considered.
of alterations in materials over periods of time beyond which
empirical data can be used for the accurate assessment of
6. General Procedure
performance and behavior. Under very extended service peri-
6.1 Fig. 1 outlines the logical approach for the development
ods, much greater than the periods encountered in engineering
of models for the prediction of the long-term behavior of
practice, materials may become altered and may change in
materials within the EBS of a repository. The major elements
form or state. The time period, when sufficiently long, can even
in the approach are problem definition, testing, modeling,
permit the achievement of equilibrium or steady state condi-
prediction, and confirmation. It is not expected that Fig. 1 will
tions and render kinetic factors, which govern rates of reac-
apply exactly to every situation, especially as to the starting
tions, to be much less important. This practice is intended for
point and the number and type of iterations necessary to obtain
use specifically for materials proposed for use in an EBS that
validated alteration models. However, it is likely that a given
contains high-level nuclear waste. These packages are to be
plan will contain all of the elements described, as well as a
emplaced in deep geologic repositories in which retrieval after
quality assurance program as discussed in Section 27 Details
closure is not contemplated – cf. 10.2 on scope of testing.
on these elements are given in Sections 7-26.
Various U.S. Government regulations pertinent to repository
disposal in the United States are as follows:
PROBLEM DEFINITION
5.1.1 Public Law 97–425, the Nuclear Waste Policy Act of
1982, provides for the deep geologic disposal of high-level
7. Scope
radioactive waste through a system of multiple barriers. Li-
7.1 Important to predictions of long-term behavior of re-
censing of such disposal will be done by the U.S. Nuclear
pository materials are the following: the identification of
Regulatory Commission (NRC).
environmental conditions; waste-package concepts: candidate
5.1.2 The NRC regulations in Part 60.113 of Title 10 of the
materials for waste packages; the form of the waste; alteration
Code of Federal Regulations (CFR) provide that containment
modes, analog materials; and literature surveys.
of radionuclides shall be substantially complete for a period
7.2 In this practice, methods are recommended for the
that shall be no less than 300 years nor more than 1000 years,
development of predictive models for long-term alterations of
unless otherwise permitted by the NRC. Any release of
EBS materials, including waste packages and waste forms, that
radionuclides after the containment period shall be a gradual
are proposed for use in the geologic disposal of high-level
release and limited to certain small fractional amounts based on
radioactive wastes. This practice is intended as an aid in
the calculated inventory present at 1000 years after closure.
assessments of performance of materials proposed for use in
These are general provisions, for the EBS, for which only
systems designed to function either for containment of radio-
anticipated processes and events need to be considered.
nuclides or the control of release rates of radionuclides.
5.1.3 The regulations of the U.S. Environmental Protection
7.3 This practice outlines a logical approach for predicting
Agency (EPA) in Part 191 of Title 40 of the CFR provide that
the behavior of materials over times that greatly exceed the
cumulative releases of radionuclides from the disposal
time over which experimental data can be obtained. It empha-
system—this refers to the total system performance not just the
sizes accelerated tests and/or the use of models that are based
EBS performance—for 10 000 years after disposal shall have
on suitable and adequate mechanisti
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