ASTM C1062-00(2014)
(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 units...
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Designation: C1062 − 00 (Reapproved 2014)
Standard Guide for
Design, Fabrication, and Installation of Nuclear Fuel
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 1.2.2.1 This guide does not address special dissolution
processes that may require substantially different equipment or
1.1 It is the intent of this guide to set forth criteria and
pose different hazards than those associated with the fuel types
procedures for the design, fabrication and installation of
noted above. Examples of precluded cases are electrolytic
nuclear fuel dissolution facilities. This guide applies to and
dissolution and sodium-bonded fuels processing. The guide
encompasses all processing steps or operations beyond the fuel
does not address the design and fabrication of continuous
shearing operation (not covered), up to and including the
dissolvers.
dissolving accountability vessel.
1.2.3 Ancillary or auxiliary facilities (for example, steam,
1.2 Applicability and Exclusions:
cooling water, electrical services) are not covered. Cold chemi-
1.2.1 Operations—This guide does not cover the operation
cal feed considerations are addressed briefly.
of nuclear fuel dissolution facilities. Some operating consider-
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps in-
ations are noted to the extent that these impact upon or
cidental to the preparation of spent fuel assemblies for disso-
influence design.
lution reprocessing are not covered by this guide. This exclu-
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel el-
sion applies to thermal treatment steps such as “Voloxidation”
ement geometry, and fuel manufacturing methods are subject
to drive off gases prior to dissolution, to mechanical decladding
to continuous change in response to the demands of new
operations or process steps associated with fuel elements
reactor designs and requirements. These changes preclude the
disassembly and removal of end fittings, to chopping and
inclusion of design considerations for dissolvers suitable for
shearing operations, and to any other pretreatment operations
the processing of all possible fuel types. This guide will only
judged essential to an efficient nuclear fuels dissolution step.
address equipment associated with dissolution cycles for those
1.2.5 Fundamentals—This guide does not address specific
fuels that have been used most extensively in reactors as of the
chemical, physical or mechanical technology, fluid mechanics,
time of issue (or revision) of this guide. (See Appendix X1.)
stress analysis or other engineering fundamentals that are also
1.2.2 Processes—This guide covers the design, fabrication
applied in the creation of a safe design for nuclear fuel
and installation of nuclear fuel dissolution facilities for fuels of
dissolution facilities.
the type currently used in Pressurized Water Reactors (PWR).
1.3 The values stated in inch-pound units are to be regarded
Boiling Water Reactors (BWR), Pressurized Heavy Water
as standard. The values given in parentheses are mathematical
Reactors (PHWR) and Heavy Water Reactors (HWR) and the
conversions to SI units that are provided for information only
fuel dissolution processing technologies discussed herein.
and are not considered standard.
However, much of the information and criteria presented may
1.4 This standard does not purport to address all of the
be applicable to the equipment for other dissolution processes
safety concerns, if any, associated with its use. It is the
such as for enriched uranium-aluminum fuels from typical
responsibility of the user of this standard to establish appro-
research reactors, as well as for dissolution processes for some
priate safety and health practices and determine the applica-
thorium and plutonium-containing fuels and others. The guide
bility of regulatory limitations prior to use.
does not address equipment design for the dissolution of high
burn-up or mixed oxide fuels.
2. Referenced Documents
2.1 Industry and National Consensus Standards—Industry
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
and national consensus standards applicable in whole or in part
Processing.
to the design, fabrication, and installation of nuclear fuel
Current edition approved June 1, 2014. Published June 2014. Originally
dissolution facilities are referenced throughout this guide and
approved in 1986. Last previous edition approved in 2008 as C1062 – 00 (2008).
DOI: 10.1520/C1062-00R14. include the following:
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1062 − 00 (2014)
2.2 ASTM Standards: 3.2 Definitions of Terms Specific to This Standard:
C1010 Guide for Acceptance, Checkout, and Pre- 3.2.1 accident—an unplanned event that could result in
Operational Testing of a Nuclear Fuels Reprocessing unacceptable levels of any of the following:
Facility (Withdrawn 2001) 3.2.1.1 equipment damage,
C1217 Guide for Design of Equipment for Processing 3.2.1.2 injury to personnel,
Nuclear and Radioactive Materials
3.2.1.3 downtime or outage,
2.3 ASME Standards: 3.2.1.4 release of hazardous materials (radioactive or non-
ASME Boiler and Pressure Vessel Code, Sections II, V, VIII, radioactive).
and IX 3.2.1.5 radiation exposure to personnel, and
ASME NQA-1 Quality Assurance Requirements for Nuclear
3.2.1.6 criticality.
Facility Applications 3.2.2 accountability—the keeping of records on and the
2.4 ANS Standard: responsibility associated with being accountable for the
ANS Glossary of Terms in Nuclear Science and Technology amount of fissile materials entering and leaving a plant, a
(ANS Glossary) location, or a processing step.
ANS 8.1 Nuclear Criticality Safety in Operations with Fis-
3.2.3 basic data—the fundamental chemical, physical, and
sionable Materials Outside Reactors
mathematical values, formulas, and principles, and the defini-
ANS 8.3 Criticality Accident Alarm System
tive criteria that have been documented and accepted as the
ANS 8.9 Nuclear Criticality Safety Criteria for Steel-Pipe
basis for facilities design.
Intersections Containing Aqueous Solutions of Fissile
3.2.4 double contingency principle—the use of methods,
Materials
measures, or factors of safety in the design of nuclear facilities
ANS 57.8 Fuel Assembly Identification
such that at least two unlikely, independent, and concurrent
2.5 Federal Regulations —Federal Regulations that are
changes in process or operating conditions are required before
specifically applicable in whole or in part to the design,
a criticality accident is possible.
fabrication, and installation of nuclear fuel dissolution facilities
3.2.5 eructation—a surface eruption in a tank, vessel, or
include the following:
liquefied pool caused by the spontaneous release of gas or
10 CFR 50 Licensing of Production and Utilization Facilities
vapor, or both, from within the liquid. An eructation may bear
10 CFR 50, App B Quality Assurance Criteria for Nuclear
some resemblance to the flashing of superheated water; but it
Power Plants and Fuel Reprocessing Plants
best resembles a burping action that may or may not be
2.6 This guide does not purport to list all standards, codes,
accompanied by dispersion of liquid droplets or particulates, or
or federal regulations, or combinations thereof that may apply
both, and by a variable degree of liquid splashing. The
to nuclear fuel dissolution facilities design.
potential for eructation is most often caused by an excessive
heating rate combined with an inadequate agitation condition.
3. Terminology
3.2.6 geometrically favorable—a term applied to a vessel or
3.1 General: system having dimensions and a shape or configuration that
provides assurance that a criticality incident cannot occur in the
3.1.1 The terminology used in this guide is intended to
conform with industry practice insofar as is practicable, but the vessel or system under a given set of conditions. The given
conditions require that the isotopic composition, form,
following terms are of a restricted nature, specifically appli-
cable to this guide. Other terms and their definitions are concentration, and density of fissile materials in the system will
duplicate those used in preparation of the criticality analysis.
contained in the ANS Glossary.
3.1.2 shall, should, and may—The word “shall” denotes a These variables will remain within conservatively chosen
limits, and moderator and reflector conditions will be within
requirement, the word “should” denotes a recommendation and
the word “may” indicates permission, neither a requirement some permitted range.
nor a recommendation. In order to conform with this guide, all
3.2.7 poison or poisoned—any material used to minimize
actions or conditions shall be in accordance with its require-
the potential for criticality, usually containing quantities of one
ments but they need not conform with its recommendations.
of the chemical elements having a high neutron absorption
cross-section, for example, boron, cadmium, gadolinium, etc.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM 4. Significance and Use
Standards volume information, refer to the standard’s Document Summary page on
4.1 The purpose of this guide is to provide information that
the ASTM website.
The last approved version of this historical standard is referenced on will help to ensure that nuclear fuel dissolution facilities are
www.astm.org.
conceived, designed, fabricated, constructed, and installed in
Available from American Society of Mechanical Engineers (ASME), ASME
an economic and efficient manner. This guide will help
International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
facilities meet the intended performance functions, eliminate or
www.asme.org.
Available from American Nuclear Society, 555f N. Kensington Ave., La Grange
minimize the possibility of nuclear criticality and provide for
Park, IL 60526.
the protection of both the operator personnel and the public at
Available from U.S. Government Printing Office Superintendent of Documents,
large under normal and abnormal (emergency) operating con-
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.access.gpo.gov. ditions as well as under credible failure or accident conditions.
C1062 − 00 (2014)
5. General Requirements assurance, chemical or physical test results, inspections, and
other records that bear on the condition, safety, or integrity of
5.1 Basic Data and Design Criteria—The fundamental data
the dissolution system facilities shall be available for audit
and design criteria that form the basis for facilities design shall
purposes at any time subsequent to their creation.
be documented in an early stage such that evolving plant
concepts and engineering calculations have a solid and trace-
6. Equipment
able origin or foundation. Design criteria can be included in an
owner/client prepared data document or, when the owner/client
6.1 Design Considerations—The general principles used to
so instructs, they may be selected or developed by the
design dissolvers for nuclear fuels are essentially the same as
responsible design, organization. Values, formulas, equations,
those widely employed in the design of processing equipment
and other data should derive from proven and scientifically and
in the chemical industry. Design of nuclear processing facilities
technically sound sources. Any and all changes to the basic
presents three additional considerations: the possibility of
data shall be documented and dated. Procedural requirements
nuclear criticality, the dissipation of heat created by radioactive
associated with the authentication, documentation, and reten-
decay, and the provision for the adequate containment of
tion of the data base should be essentially equivalent to, and
radioactive contaminants under both normal and abnormal
meet the intent of, ASME NQA-1.
conditions. The latter consideration demands a degree of
quality and the application of quality assurance procedures that
5.2 Responsibility for Basic Data—The production,
are in excess of those that are normally required in the
authentication, and issue of the basic data document should be
chemical industry.
the responsibility of the owner/client. However, this responsi-
bility may be delegated. 6.1.1 General considerations and accepted good practice in
regard to the design of dissolvers and other processing vessels
5.2.1 The Architect-Engineering (AE) organization charged
for nuclear and radioactive materials is contained in guide
with design and engineering responsibility for the nuclear fuel
C1217.
dissolution facilities is generally held responsible for the
adequacy, appropriateness, and completeness of the basic data. 6.1.2 Design of dissolution equipment and facilities shall
The AE shall indicate the acceptance of this responsibility by include provisions to minimize the release of radioactive
a signed client/AE acceptance document in testimony thereof. material from process vessels and equipment (including pipes
Such an acceptance document should be executed within 90
or lines connecting to vessels or areas that are not normally
days after receipt of the basic data document. contaminated with radioactive material, such as cold reagent
and instrument air) or confinement (for example, shielding cell
5.3 Quality Assurance—A formalized quality assurance pro-
walls) during normal and foreseeable abnormal conditions of
gram shall be conducted as required by 10 CFR 50, App B.
operation, maintenance, and decontamination.
This program shall be in general accordance with ASME
6.1.3 Offgas, vapor, droplet, and foaming disengagement
NQA-1.
space, equivalent to approximately 100 % freeboard should be
5.4 Personnel—Personnel associated with facility design
included in sizing the dissolver. The dissolver fuel baskets
and construction should collectively have the training,
should be sized so that the fuel charge occupies no more than
experience, and competence to understand, analyze, engineer,
75 % of the basket depth. This will help to ensure confinement
and resolve questions or problems associated with their as-
of hulls and metal fragments during the dissolution cycle. Fuel
signed ta
...
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 2008) C1062 − 00 (Reapproved 2014)
Standard Guide for
Design, Fabrication, and Installation of Nuclear Fuel
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
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 does not purport to address all of the safety concerns, if any, 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.
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, 2008June 1, 2014. Published July 2008 June 2014. Originally approved in 1986. Last previous edition approved in 20002008 as
C1062 – 00.C1062 – 00 (2008). DOI: 10.1520/C1062-00R08.10.1520/C1062-00R14.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1062 − 00 (2014)
2. Referenced Documents
2.1 Industry and National Consensus Standards—Industry and national consensus standards applicable in whole or in part to
the design, fabrication, and installation of nuclear fuel dissolution facilities are referenced throughout this guide and include the
following:
2.2 ASTM Standards:
C1010 Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels Reprocessing Facility (Withdrawn
2001)
C1217 Guide for Design of Equipment for Processing Nuclear and Radioactive Materials
2.3 ASME Standards:
ASME Boiler and Pressure Vessel Code, Sections II, V, VIII, and IX
ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications
2.4 ANS Standard:
ANS Glossary of Terms in Nuclear Science and Technology (ANS Glossary)
ANS 8.1 Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors
ANS 8.3 Criticality Accident Alarm System
ANS 8.9 Nuclear Criticality Safety Criteria for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials
ANS 57.8 Fuel Assembly Identification
2.5 Federal Regulations —Federal Regulations that are specifically applicable in whole or in part to the design, fabrication, and
installation of nuclear fuel dissolution facilities include the following:
10 CFR 50 Licensing of Production and Utilization Facilities
10 CFR 50, App B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
2.6 This guide does not purport to list all standards, codes, and/or federal regulations or federal regulations, or combinations
thereof that may apply to nuclear fuel dissolution facilities design.
3. Terminology
3.1 General:
3.1.1 The terminology used in this guide is intended to conform with industry practice insofar as is practicable, but the following
terms are of a restricted nature, specifically applicable to this guide. Other terms and their definitions are contained in the ANS
Glossary.
3.1.2 shall, should, and may—The word “shall” denotes a requirement, the word “should” denotes a recommendation and the
word “may” indicates permission, neither a requirement nor a recommendation. In order to conform with this guide, all actions
or conditions shall be in accordance with its requirements but they need not conform with its recommendations.
3.2 Definitions of Terms Specific to This Standard:
3.2.1 accident—an unplanned event that could result in unacceptable levels of any of the following:
3.2.1.1 equipment damage,
3.2.1.2 injury to personnel,
3.2.1.3 downtime or outage,
3.2.1.4 release of hazardous materials (radioactive or nonradioactive).
3.2.1.5 radiation exposure to personnel, and
3.2.1.6 criticality.
3.2.2 accountability—the keeping of records on and the responsibility associated with being accountable for the amount of
fissile materials entering and leaving a plant, a location, or a processing step.
3.2.3 basic data—the fundamental chemical, physical, and mathematical values, formulas, and principles, and the definitive
criteria that have been documented and accepted as the basis for facilities design.
3.2.4 double contingency principle—the use of methods, measures, or factors of safety in the design of nuclear facilities such
that at least two unlikely, independent, and concurrent changes in process or operating conditions are required before a criticality
accident is possible.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
The last approved version of this historical standard is referenced on www.astm.org.
Available from American Society of Mechanical Engineers (ASME), ASME International Headquarters, ThreeTwo Park Ave., New York, NY 10016-5990,
http://www.asme.org.
Available from American Nuclear Society, 555f N. Kensington Ave., La Grange Park, IL 60526.
Available from U.S. Government Printing Office Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.access.gpo.gov.
C1062 − 00 (2014)
3.2.5 eructation—a surface eruption in a tank, vessel, or liquefied pool caused by the spontaneous release of gas or vapor, or
both, from within the liquid. An eructation may bear some resemblance to the flashing of superheated water; but it best resembles
a burping action that may or may not be accompanied by dispersion of liquid droplets or particulates, or both, and by a variable
degree of liquid splashing. The potential for eructation is most often caused by an excessive heating rate combined with an
inadequate agitation condition.
3.2.6 geometrically favorable—a term applied to a vessel or system having dimensions and a shape or configuration that
provides assurance that a criticality incident cannot occur in the vessel or system under a given set of conditions. The given
conditions require that the isotopic composition, form, concentration, and density of fissile materials in the system will duplicate
those used in preparation of the criticality analysis. These variables will remain within conservatively chosen limits, and moderator
and reflector conditions will be within some permitted range.
3.2.7 poison or poisoned—any material used to minimize the potential for criticality, usually containing quantities of one of the
chemical elements having a high neutron absorption cross-section, for example, boron, cadmium, gadolinium, etc.
4. 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.
5. General Requirements
5.1 Basic Data and Design Criteria—The fundamental data and design criteria that form the basis for facilities design shall be
documented in an early stage such that evolving plant concepts and engineering calculations have a solid and traceable origin or
foundation. Design criteria can be included in an owner/client prepared data document or, when the owner/client so instructs, they
may be selected or developed by the responsible design, organization. Values, formulas, equations, and other data should derive
from proven and scientifically and technically sound sources. Any and all changes to the basic data shall be documented and dated.
Procedural requirements associated with the authentication, documentation, and retention of the data base should be essentially
equivalent to, and meet the intent of, ASME NQA-1.
5.2 Responsibility for Basic Data—The production, authentication, and issue of the basic data document should be the
responsibility of the owner/client. However, this responsibility may be delegated.
5.2.1 The Architect-Engineering (AE) organization charged with design and engineering responsibility for the nuclear fuel
dissolution facilities is generally held responsible for the adequacy, appropriateness, and completeness of the basic data. The AE
shall indicate the acceptance of this responsibility by a signed client/AE acceptance document in testimony thereof. Such an
acceptance document should be executed within 90 days after receipt of the basic data document.
5.3 Quality Assurance—A formalized quality assurance program shall be conducted as required by 10 CFR 50, App B. This
program shall be in general accordance with ASME NQA-1.
5.4 Personnel—Personnel associated with facility design and construction should collectively have the training, experience, and
competence to understand, analyze, engineer, and resolve questions or problems associated with their assigned tasks.
5.4.1 Records shall be kept showing names and responsibilities of personnel involved with and responsible for the design,
fabrication, inspection, and installation of nuclear fuel dissolving facilities for purposes of auditing quality assurance (QA) records.
5.5 Degree of Quality—The quality and integrity of materials and workmanship associated with the design, fabrication, and
installation of nuclear fuels dissolution facilities shall be commensurate with calculated, demonstrable needs. Such needs arise
from known and perceived risks, given physical and chemical principles, and applicable codes and regulations.
5.5.1 In setting forth the need for any given level of quality or integrity, the organization or individual responsible for making
any such determination shall document the tests and acceptance criteria by which attainment or conformity is to be judged.
Attainment or conformity verification requirements should be written into the Quality Assurance Inspection procedures.
5.6 Records Retention—All records pertaining to the basic data, design calculations, computer analysis, quality, quality
assurance, chemical or physical test results, inspections, and other records that bear on the condition, safety, or integrity of the
dissolution system facilities shall be available for audit purposes at any time subsequent to their creation.
6. Equipment
6.1 Design Considerations—The general principles used to design dissolvers for nuclear fuels are essentially the same as those
widely employed in the design of processing equipment in the chemical industry. Design of nuclear processing facilities presents
thr
...
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