ASTM C1062-00(2008)
(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
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 that are ...
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Designation: C1062 − 00 (Reapproved2008)
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:
coolingwater,electricalservices)arenotcovered.Coldchemi-
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
todriveoffgasespriortodissolution,tomechanicaldecladding
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 ofASTM 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
CurrenteditionapprovedJune1,2008.PublishedJuly2008.Originallyapproved
dissolution facilities are referenced throughout this guide and
in 1986. Last previous edition approved in 2000 as C1062 – 00. DOI: 10.1520/
C1062-00R08. include the following:
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1062 − 00 (2008)
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-
ASMEBoilerandPressureVesselCode, SectionsII,V,VIII, radioactive).
and IX 3.2.1.5 radiation exposure to personnel, and
ASME NQA-1 QualityAssurance 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,andinstallationofnuclearfueldissolutionfacilities
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
10CFR50 LicensingofProductionandUtilizationFacilities
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,
accompaniedbydispersionofliquiddropletsorparticulates,or
and/or federal regulations that may apply to nuclear fuel
both, and by a variable degree of liquid splashing. The
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
system having dimensions and a shape or configuration that
3.1 General:
3.1.1 The terminology used in this guide is intended to providesassurancethatacriticalityincidentcannotoccurinthe
vessel or system under a given set of conditions. The given
conformwithindustrypracticeinsofarasispracticable,butthe
following terms are of a restricted nature, specifically appli- conditions require that the isotopic composition, form, concen-
tration, and density of fissile materials in the system will
cable to this guide. Other terms and their definitions are
contained in the ANS Glossary. duplicate those used in preparation of the criticality analysis.
These variables will remain within conservatively chosen
3.1.2 shall, should, and may—The word “shall” denotes a
requirement,theword“should”denotesarecommendationand limits, and moderator and reflector conditions will be within
some permitted range.
the word “may” indicates permission, neither a requirement
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
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facilitiesmeettheintendedperformancefunctions,eliminateor
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AvailablefromAmericanNuclearSociety,555fN.KensingtonAve.,LaGrange
minimize the possibility of nuclear criticality and provide for
Park, IL 60526.
the protection of both the operator personnel and the public at
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large under normal and abnormal (emergency) operating con-
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www.access.gpo.gov. ditions as well as under credible failure or accident conditions.
C1062 − 00 (2008)
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/clientprepareddatadocumentor,whentheowner/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
andotherdatashouldderivefromprovenandscientificallyand
inthechemicalindustry.Designofnuclearprocessingfacilities
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
nuclearcriticality,thedissipationofheatcreatedbyradioactive
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
qualityandtheapplicationofqualityassuranceproceduresthat
5.2 Responsibility for Basic Data—The production, authen-
are in excess of those that are normally required in the
tication, and issue of the basic data document should be the
chemical industry.
responsibility of the owner/client. However, this responsibility
6.1.1 General considerations and accepted good practice in
may be delegated.
regard to the design of dissolvers and other processing vessels
5.2.1 TheArchitect-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—Aformalizedqualityassurancepro-
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, experi-
should be sized so that the fuel charge occupies no more than
ence, and competence to understand, analyze, engineer, and
75 % of the basket depth. This will help to ensure confinement
resolve questions or problems associated with their assigned
of hulls and metal fragments during the dissolution cycle. Fuel
tasks.
basket perforations (openings) should be limited in size to
5.4.1 Records shall be kept showing names and responsi-
retain metal fragments and yet allow free flow of dissolvent
bilities of personnel
...
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