ASTM C1553-21
(Guide)Standard Guide for Drying of Spent Nuclear Fuel
Standard Guide for Drying of Spent Nuclear Fuel
SIGNIFICANCE AND USE
4.1 Drying of the SNF and fuel cavity of the SNF container and its internals is needed to prepare for sealed dry storage, transportation, or permanent disposal at a repository. This guide provides technical information for use in determining the forms of water that need to be considered when choosing a drying process. This guide provides information to aid in (a) selecting a drying system, (b) selecting a drying method, and (c) demonstrating that adequate dryness was achieved (see Annex A2).
4.2 The considerations affecting drying processes include:
4.2.1 Water remaining on and in commercial, research, and production reactor spent nuclear fuels after removal from wet storage may become an issue when the fuel is sealed in a dry storage system or transport cask. The movement to a dry storage environment typically results in an increase in fuel temperature, which may be sufficient to cause the release of water from the fuel. The water release coupled with the temperature increase in a sealed container may result in container pressurization, corrosion of fuel or assembly structures, or both, that could affect retrieval of the fuel, and container corrosion.
4.2.2 Removal of the water associated with the SNF may be accomplished by a variety of technologies including heating, imposing a vacuum over the system, flushing the system with dry gases, and combinations of these and other similar processes.
4.2.3 Water removal processes are time, temperature, and pressure-dependent. Residual water in some form(s) should be anticipated.
4.2.4 Drying processes may not readily remove the water that was retained in porous materials, capillaries, sludge, CRUD, physical features that retain water and as thin wetted surface films. Water trapped within breached SNF may be especially difficult to remove.
4.2.5 Drying processes may be even less successful in removing bound water from the SNF and associated materials because removal of bound water will only occur when the t...
SCOPE
1.1 This guide discusses three steps in preparing spent nuclear fuel (SNF) for placement in a sealed dry storage system: (1) evaluating the needs for drying the SNF after removal from a water storage pool and prior to placement in dry storage, (2) drying the SNF, and (3) demonstrating that adequate dryness has been achieved.
1.1.1 The scope of SNF includes nuclear fuel of any design (fuel core, clad materials, and geometric configuration) discharged from power reactors and research reactors and its condition as impacted by reactor operation, handling, and water storage.
1.1.2 The guide addresses drying methods and their limitations when applied to the drying of SNF that has been stored in water pools. The guide discusses sources and forms of water that may remain in the SNF, the container, or both after the drying process has been completed. It also discusses the important and potential effects of the drying process and any residual water on fuel integrity and container materials during the dry storage period. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments.
1.1.3 The basic issues in drying are: (1) to determine how dry the SNF must be in order to prevent problems with fuel retrievability, container pressurization, or container corrosion during storage, handling, and transfer, and (2) to demonstrate that adequate dryness has been achieved. Achieving adequate dryness may be straightforward for intact commercial fuel but complex for any SNF where the cladding is breached prior to or during placement and storage at the spent fuel pools. Challenges in achieving adequate dryness may also result from the presence of sludge, CRUD, and any other hydrated compounds. These may be transferred with the SNF to the storage con...
General Information
Relations
Buy Standard
Standards Content (Sample)
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.
Designation: C1553 − 21
Standard Guide for
1
Drying of Spent Nuclear Fuel
This standard is issued under the fixed designation C1553; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope compounds. These may be transferred with the SNF to the
storage container and may hold water and resist drying.
1.1 This guide discusses three steps in preparing spent
1.1.4 Units are given in both SI and non-SI units as is
nuclear fuel (SNF) for placement in a sealed dry storage
industrystandard.Insomecases,mathematicalequivalentsare
system: (1) evaluating the needs for drying the SNF after
given in parentheses.
removal from a water storage pool and prior to placement in
1.2 This standard does not purport to address all of the
dry storage, (2) drying the SNF, and (3) demonstrating that
safety concerns, if any, associated with its use. It is the
adequate dryness has been achieved.
responsibility of the user of this standard to establish appro-
1.1.1 The scope of SNF includes nuclear fuel of any design
priate safety, health, and environmental practices and deter-
(fuel core, clad materials, and geometric configuration) dis-
mine the applicability of regulatory limitations prior to use.
charged from power reactors and research reactors and its
1.3 This international standard was developed in accor-
condition as impacted by reactor operation, handling, and
dance with internationally recognized principles on standard-
water storage.
ization established in the Decision on Principles for the
1.1.2 The guide addresses drying methods and their limita-
Development of International Standards, Guides and Recom-
tionswhenappliedtothedryingofSNFthathasbeenstoredin
mendations issued by the World Trade Organization Technical
water pools. The guide discusses sources and forms of water
Barriers to Trade (TBT) Committee.
that may remain in the SNF, the container, or both after the
drying process has been completed. It also discusses the
2. Referenced Documents
important and potential effects of the drying process and any
2
2.1 ASTM Standards:
residual water on fuel integrity and container materials during
the dry storage period. The effects of residual water are C859Terminology Relating to Nuclear Materials
discussed mechanistically as a function of the container ther- C1174Guide for Evaluation of Long-Term Behavior of
mal and radiological environment to provide guidance on Materials Used in Engineered Barrier Systems (EBS) for
situations that may require extraordinary drying methods, Geological Disposal of High-Level Radioactive Waste
specialized handling, or other treatments. C1562Guide for Evaluation of Materials Used in Extended
1.1.3 The basic issues in drying are: (1) to determine how Service of Interim Spent Nuclear Fuel Dry Storage Sys-
tems
dry the SNF must be in order to prevent problems with fuel
3
retrievability, container pressurization, or container corrosion 2.2 ANSI/ANS Standards:
during storage, handling, and transfer, and (2) to demonstrate ANSI/ANS 8.1-1998Nuclear Criticality Safety in Opera-
that adequate dryness has been achieved. Achieving adequate tions with Fissionable Materials Outside Reactors
ANSI/ANS-8.7-1998Nuclear Criticality Safety in the Stor-
dryness may be straightforward for intact commercial fuel but
complex for any SNF where the cladding is breached prior to age of Fissile Materials
ANSI/ANS-57.9American National Standard Design Crite-
or during placement and storage at the spent fuel pools.
Challengesinachievingadequatedrynessmayalsoresultfrom ria for Independent Spent Fuel Storage Installation (Dry
Type)
the presence of sludge, CRUD, and any other hydrated
1 2
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
High Level Waste. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Oct. 1, 2021. Published November 2021. Originally the ASTM website.
3
approved in 2008. Last previous edition approved in 2016 as C1553–16. DOI: Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
10.1520/C1553-21. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohoc
...
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: C1553 − 16 C1553 − 21
Standard Guide for
1
Drying Behavior of Spent Nuclear Fuel
This standard is issued under the fixed designation C1553; 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 discusses three steps in preparing spent nuclear fuel (SNF) for placement in a sealed dry storage system: (1)
evaluating the needs for drying the SNF after removal from a water storage pool and prior to placement in dry storage, (2) drying
the SNF, and (3) demonstrating that adequate dryness has been achieved.
1.1.1 The scope of SNF includes nuclear fuel of any design (fuel core, clad materials, and geometric configuration) discharged
from power reactors and research reactors and its condition as impacted by reactor operation, handling, and water storage.
1.1.2 The guide addresses drying methods and their limitations when applied to the drying of SNF that has been stored in water
pools. The guide discusses sources and forms of water that may remain in the SNF, the container, or both after the drying process
has been completed. It also discusses the important and potential effects of the drying process and any residual water on fuel
integrity and container materials during the dry storage period. The effects of residual water are discussed mechanistically as a
function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary
drying methods, specialized handling, or other treatments.
1.1.3 The basic issues in drying are: (1) to determine how dry the SNF must be in order to prevent problems with fuel
retrievability, container pressurization, or container corrosion during storage, handling, and transfer, and (2) to demonstrate that
adequate dryness has been achieved. Achieving adequate dryness may be straightforward for undamagedintact commercial fuel but
complex for any SNF where cladding damage has occurred the cladding is breached prior to or during placement and storage at
the spent fuel pools. Challenges in achieving adequate dryness may also result from the presence of sludge, CRUD, and any other
hydrated compounds. These may be transferred with the SNF to the storage container and may hold water and resist drying.
1.1.4 Units are given in both SI and non-SI units as is industry standard. In some cases, mathematical equivalents are given in
parentheses.
1.2 This standard only discusses SNF drying and does not purport to address all of the handling and safety concerns, if any,
associated with the drying process(es). its use. It is the responsibility of the user of this standard to establish appropriate safety
safety, health, and healthenvironmental practices and to meet regulatory requirements prior to and during use of the
standard.determine the applicability of regulatory limitations prior to use.
1.3 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.
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 July 1, 2016Oct. 1, 2021. Published November 2016November 2021. Originally approved in 2008. Last previous edition approved in 20082016
as C1553 – 08.C1553 – 16. DOI: 10.1520/C1553-16.10.1520/C1553-21.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1553 − 21
2. Referenced Documents
2
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C1174 Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological
Disposal of High-Level Radioactive Waste
C1562 Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
3
2.2 ANSI/ANS Standards:
ANSI/ANS 8.1-1998 Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors
ANSI/ANS-8.7-1998 Nuclear Criticality Safety in the Storage of F
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.