ASTM C1062-23
(Guide)Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities
Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities
SIGNIFICANCE AND USE
4.1 The purpose of this guide is to provide information that will help to ensure that nuclear fuel dissolution facilities are conceived, designed, fabricated, constructed, and installed in an economic and efficient manner. This guide will help facilities meet the intended performance functions, eliminate or minimize the possibility of nuclear criticality and provide for the protection of both the operator personnel and the public at large under normal and abnormal (emergency) operating conditions as well as under credible failure or accident conditions.
SCOPE
1.1 It is the intent of this guide to set forth criteria and procedures for the design, fabrication and installation of nuclear fuel dissolution facilities. This guide applies to and encompasses all processing steps or operations beyond the fuel shearing operation (not covered), up to and including the dissolving accountability vessel.
1.2 Applicability and Exclusions:
1.2.1 Operations—This guide does not cover the operation of nuclear fuel dissolution facilities. Some operating considerations are noted to the extent that these impact upon or influence design.
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel element geometry, and fuel manufacturing methods are subject to continuous change in response to the demands of new reactor designs and requirements. These changes preclude the inclusion of design considerations for dissolvers suitable for the processing of all possible fuel types. This guide will only address equipment associated with dissolution cycles for those fuels that have been used most extensively in reactors as of the time of issue (or revision) of this guide. (See Appendix X1.)
1.2.2 Processes—This guide covers the design, fabrication and installation of nuclear fuel dissolution facilities for fuels of the type currently used in Pressurized Water Reactors (PWR). Boiling Water Reactors (BWR), Pressurized Heavy Water Reactors (PHWR) and Heavy Water Reactors (HWR) and the fuel dissolution processing technologies discussed herein. However, much of the information and criteria presented may be applicable to the equipment for other dissolution processes such as for enriched uranium-aluminum fuels from typical research reactors, as well as for dissolution processes for some thorium and plutonium-containing fuels and others. The guide does not address equipment design for the dissolution of high burn-up or mixed oxide fuels.
1.2.2.1 This guide does not address special dissolution processes that may require substantially different equipment or pose different hazards than those associated with the fuel types noted above. Examples of precluded cases are electrolytic dissolution and sodium-bonded fuels processing. The guide does not address the design and fabrication of continuous dissolvers.
1.2.3 Ancillary or auxiliary facilities (for example, steam, cooling water, electrical services) are not covered. Cold chemical feed considerations are addressed briefly.
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps incidental to the preparation of spent fuel assemblies for dissolution reprocessing are not covered by this guide. This exclusion applies to thermal treatment steps such as “Voloxidation” to drive off gases prior to dissolution, to mechanical decladding operations or process steps associated with fuel elements disassembly and removal of end fittings, to chopping and shearing operations, and to any other pretreatment operations judged essential to an efficient nuclear fuels dissolution step.
1.2.5 Fundamentals—This guide does not address specific chemical, physical or mechanical technology, fluid mechanics, stress analysis or other engineering fundamentals that are also applied in the creation of a safe design for nuclear fuel dissolution facilities.
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI unit...
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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: C1062 − 23
Standard Guide for
Design, Fabrication, and Installation of Nuclear Fuel
1
Dissolution Facilities
This standard is issued under the fixed designation C1062; 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 pose different hazards than those associated with the fuel types
noted above. Examples of precluded cases are electrolytic
1.1 It is the intent of this guide to set forth criteria and
dissolution and sodium-bonded fuels processing. The guide
procedures for the design, fabrication and installation of
does not address the design and fabrication of continuous
nuclear fuel dissolution facilities. This guide applies to and
dissolvers.
encompasses all processing steps or operations beyond the fuel
1.2.3 Ancillary or auxiliary facilities (for example, steam,
shearing operation (not covered), up to and including the
cooling water, electrical services) are not covered. Cold chemi-
dissolving accountability vessel.
cal feed considerations are addressed briefly.
1.2 Applicability and Exclusions:
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps in-
1.2.1 Operations—This guide does not cover the operation
cidental to the preparation of spent fuel assemblies for disso-
of nuclear fuel dissolution facilities. Some operating consider-
lution reprocessing are not covered by this guide. This exclu-
ations are noted to the extent that these impact upon or
sion applies to thermal treatment steps such as “Voloxidation”
influence design.
to drive off gases prior to dissolution, to mechanical decladding
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel el-
operations or process steps associated with fuel elements
ement geometry, and fuel manufacturing methods are subject
disassembly and removal of end fittings, to chopping and
to continuous change in response to the demands of new
shearing operations, and to any other pretreatment operations
reactor designs and requirements. These changes preclude the
judged essential to an efficient nuclear fuels dissolution step.
inclusion of design considerations for dissolvers suitable for
1.2.5 Fundamentals—This guide does not address specific
the processing of all possible fuel types. This guide will only
chemical, physical or mechanical technology, fluid mechanics,
address equipment associated with dissolution cycles for those
stress analysis or other engineering fundamentals that are also
fuels that have been used most extensively in reactors as of the
applied in the creation of a safe design for nuclear fuel
time of issue (or revision) of this guide. (See Appendix X1.)
dissolution facilities.
1.2.2 Processes—This guide covers the design, fabrication
1.3 The values stated in inch-pound units are to be regarded
and installation of nuclear fuel dissolution facilities for fuels of
as standard. The values given in parentheses are mathematical
the type currently used in Pressurized Water Reactors (PWR).
conversions to SI units that are provided for information only
Boiling Water Reactors (BWR), Pressurized Heavy Water
and are not considered standard.
Reactors (PHWR) and Heavy Water Reactors (HWR) and the
1.4 This standard does not purport to address all of the
fuel dissolution processing technologies discussed herein.
safety concerns, if any, associated with its use. It is the
However, much of the information and criteria presented may
responsibility of the user of this standard to establish appro-
be applicable to the equipment for other dissolution processes
priate safety, health, and environmental practices and deter-
such as for enriched uranium-aluminum fuels from typical
mine the applicability of regulatory limitations prior to use.
research reactors, as well as for dissolution processes for some
1.5 This international standard was developed in accor-
thorium and plutonium-containing fuels and others. The guide
dance with internationally recognized principles on standard-
does not address equipment design for the dissolution of high
ization established in the Decision on Principles for the
burn-up or mixed oxide fuels.
Development of International Standards, Guides and Recom-
1.2.2.1 This guide does not address special dissolution
mendations issued by the World Trade Organization Technical
processes that may require substantially different equipment or
Barriers to Trade (TBT) Committee.
1
This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel
2. Referenced Documents
...
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: C1062 − 00 (Reapproved 2014) C1062 − 23
Standard Guide for
Design, Fabrication, and Installation of Nuclear Fuel
1
Dissolution Facilities
This standard is issued under the fixed designation C1062; 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 It is the intent of this guide to set forth criteria and procedures for the design, fabrication and installation of nuclear fuel
dissolution facilities. This guide applies to and encompasses all processing steps or operations beyond the fuel shearing operation
(not covered), up to and including the dissolving accountability vessel.
1.2 Applicability and Exclusions:
1.2.1 Operations—This guide does not cover the operation of nuclear fuel dissolution facilities. Some operating considerations are
noted to the extent that these impact upon or influence design.
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel element geometry, and fuel manufacturing methods are subject to
continuous change in response to the demands of new reactor designs and requirements. These changes preclude the inclusion of
design considerations for dissolvers suitable for the processing of all possible fuel types. This guide will only address equipment
associated with dissolution cycles for those fuels that have been used most extensively in reactors as of the time of issue (or
revision) of this guide. (See Appendix X1.)
1.2.2 Processes—This guide covers the design, fabrication and installation of nuclear fuel dissolution facilities for fuels of the type
currently used in Pressurized Water Reactors (PWR). Boiling Water Reactors (BWR), Pressurized Heavy Water Reactors (PHWR)
and Heavy Water Reactors (HWR) and the fuel dissolution processing technologies discussed herein. However, much of the
information and criteria presented may be applicable to the equipment for other dissolution processes such as for enriched
uranium-aluminum fuels from typical research reactors, as well as for dissolution processes for some thorium and plutonium-
containing fuels and others. The guide does not address equipment design for the dissolution of high burn-up or mixed oxide fuels.
1.2.2.1 This guide does not address special dissolution processes that may require substantially different equipment or pose
different hazards than those associated with the fuel types noted above. Examples of precluded cases are electrolytic dissolution
and sodium-bonded fuels processing. The guide does not address the design and fabrication of continuous dissolvers.
1.2.3 Ancillary or auxiliary facilities (for example, steam, cooling water, electrical services) are not covered. Cold chemical feed
considerations are addressed briefly.
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps incidental to the preparation of spent fuel assemblies for dissolution
reprocessing are not covered by this guide. This exclusion applies to thermal treatment steps such as “Voloxidation” to drive off
1
This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.09 on Nuclear Processing.
Current edition approved June 1, 2014April 1, 2023. Published June 2014July 2023. Originally approved in 1986. Last previous edition approved in 20082014 as
C1062 – 00 (2008).(2014). DOI: 10.1520/C1062-00R14.10.1520/C1062-23.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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C1062 − 23
gases prior to dissolution, to mechanical decladding operations or process steps associated with fuel elements disassembly and
removal of end fittings, to chopping and shearing operations, and to any other pretreatment operations judged essential to an
efficient nuclear fuels dissolution step.
1.2.5 Fundamentals—This guide does not address specific chemical, physical or mechanical technology, fluid mechanics, stress
analysis or other engineering fundamentals that are also applied in the creation of a safe design for nuclear fuel dissolution
facilities.
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical
conversions to SI units that are provided for information only and are not considered standard.
1.4 This standard do
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