ASTM C1062-00
(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
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 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.
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Designation:C1062–00
Standard Guide for
Design, Fabrication, and Installation of Nuclear Fuel
Dissolution Facilities
This standard is issued under the fixed designation C 1062; 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 dissolution and sodium-bonded fuels processing. The guide
does not address the design and fabrication of continuous
1.1 It is the intent of this guide to set forth criteria and
dissolvers.
procedures for the design, fabrication and installation of
1.2.3 Ancillary or auxiliary facilities (for example, steam,
nuclear fuel dissolution facilities. This guide applies to and
coolingwater,electricalservices)arenotcovered.Coldchemi-
encompasses all processing steps or operations beyond the fuel
cal feed considerations are addressed briefly.
shearing operation (not covered), up to and including the
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps in-
dissolving accountability vessel.
cidental to the preparation of spent fuel assemblies for disso-
1.2 Applicability and Exclusions:
lution reprocessing are not covered by this guide. This exclu-
1.2.1 Operations—This guide does not cover the operation
sion applies to thermal treatment steps such as “Voloxidation”
of nuclear fuel dissolution facilities. Some operating consider-
todriveoffgasespriortodissolution,tomechanicaldecladding
ations are noted to the extent that these impact upon or
operations or process steps associated with fuel elements
influence design.
disassembly and removal of end fittings, to chopping and
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel
shearing operations, and to any other pretreatment operations
element geometry, and fuel manufacturing methods are subject
judged essential to an efficient nuclear fuels dissolution step.
to continuous change in response to the demands of new
1.2.5 Fundamentals—This guide does not address specific
reactor designs and requirements. These changes preclude the
chemical, physical or mechanical technology, fluid mechanics,
inclusion of design considerations for dissolvers suitable for
stress analysis or other engineering fundamentals that are also
the processing of all possible fuel types. This guide will only
applied in the creation of a safe design for nuclear fuel
address equipment associated with dissolution cycles for those
dissolution facilities.
fuels that have been used most extensively in reactors as of the
1.3 This standard does not purport to address all of the
time of issue (or revision) of this guide. (See Appendix X1.)
safety concerns, if any, associated with its use. It is the
1.2.2 Processes—This guide covers the design, fabrication
responsibility of the user of this standard to establish appro-
and installation of nuclear fuel dissolution facilities for fuels of
priate safety and health practices and determine the applica-
the type currently used in Pressurized Water Reactors (PWR).
bility of regulatory limitations prior to use.
Boiling Water Reactors (BWR), Pressurized Heavy Water
Reactors (PHWR) and Heavy Water Reactors (HWR) and the
2. Referenced Documents
fuel dissolution processing technologies discussed herein.
2.1 Industry and National Consensus Standards—Industry
However, much of the information and criteria presented may
and national consensus standards applicable in whole or in part
be applicable to the equipment for other dissolution processes
to the design, fabrication, and installation of nuclear fuel
such as for enriched uranium-aluminum fuels from typical
dissolution facilities are referenced throughout this guide and
research reactors, as well as for dissolution processes for some
include the following:
thorium and plutonium-containing fuels and others. The guide
2.2 ASTM Standards:
does not address equipment design for the dissolution of high
C 1010 Guide for Acceptance, Checkout, and Pre-
burn-up or mixed oxide fuels.
Operational Testing of a Nuclear Fuels Reprocessing
1.2.2.1 This guide does not address special dissolution
Facility
processes that may require substantially different equipment or
C 1217 Guide for Design of Equipment for Processing
pose different hazards than those associated with the fuel types
Nuclear and Radioactive Materials
noted above. Examples of precluded cases are electrolytic
2.3 ASME Standards:
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
Cycle and is the direct responsibility of Subcommittee C26.09 on Nuclear Annual Book of ASTM Standards, Vol 12.01.
Processing. Available from American Society of Mechanical Engineers, 3 Park Ave., New
Current edition approved June 10, 2000. Published August 2000. York, NY 10016.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C1062
ASME Boiler and Pressure Vessel Code, Sections II, V, tive criteria that have been documented and accepted as the
VIII, and IX basis for facilities design.
ASME NQA-1 Quality Assurance Requirements for
3.2.4 double contingency principle—the use of methods,
Nuclear Facility Applications
measures, or factors of safety in the design of nuclear facilities
2.4 ANS Standard:
such that at least two unlikely, independent, and concurrent
ANS Glossary of Terms in Nuclear Science and Technology
changes in process or operating conditions are required before
(ANS Glossary)
a criticality accident is possible.
ANS 8.1 Nuclear Criticality Safety in Operations with
3.2.5 eructation—a surface eruption in a tank, vessel, or
Fissionable Materials Outside Reactors
liquefied pool caused by the spontaneous release of gas or
ANS 8.3 Criticality Accident Alarm System
vapor, or both, from within the liquid.An eructation may bear
ANS 8.9 Nuclear Criticality Safety Criteria for Steel-Pipe
some resemblance to the flashing of superheated water; but it
Intersections Containing Aqueous Solutions of Fissile
best resembles a burping action that may or may not be
Materials
accompaniedbydispersionofliquiddropletsorparticulates,or
ANS 57.8 Fuel Assembly Identification
both, and by a variable degree of liquid splashing. The
2.5 Federal Regulations —Federal Regulations that are
potential for eructation is most often caused by an excessive
specifically applicable in whole or in part to the design,
heating rate combined with an inadequate agitation condition.
fabrication,andinstallationofnuclearfueldissolutionfacilities
3.2.6 geometrically favorable—a term applied to a vessel or
include the following:
system having dimensions and a shape or configuration that
10CFR50 Licensing of Production and Utilization Facilities
providesassurancethatacriticalityincidentcannotoccurinthe
10CFR50, App B Quality Assurance Criteria for Nuclear
vessel or system under a given set of conditions. The given
Power Plants and Fuel Reprocessing Plants
conditions require that the isotopic composition, form, concen-
2.6 This guide does not purport to list all standards, codes,
tration, and density of fissile materials in the system will
and/or federal regulations that may apply to nuclear fuel
duplicate those used in preparation of the criticality analysis.
dissolution facilities design.
These variables will remain within conservatively chosen
limits, and moderator and reflector conditions will be within
3. Terminology
some permitted range.
3.1 General:
3.2.7 poison or poisoned—any material used to minimize
3.1.1 The terminology used in this guide is intended to the potential for criticality, usually containing quantities of one
conform with industry practice insofar as is practicable, but the
of the chemical elements having a high neutron absorption
following terms are of a restricted nature, specifically appli- cross-section, for example, boron, cadmium, gadolinium, etc.
cable to this guide. Other terms and their definitions are
contained in the ANS Glossary.
4. Significance and Use
3.1.2 shall, should, and may—The word “shall” denotes a
4.1 The purpose of this guide is to provide information that
requirement,theword“should”denotesarecommendationand
will help to ensure that nuclear fuel dissolution facilities are
the word “may” indicates permission, neither a requirement
conceived, designed, fabricated, constructed, and installed in
nor a recommendation. In order to conform with this guide, all
an economic and efficient manner. This guide will help
actions or conditions shall be in accordance with its require-
facilitiesmeettheintendedperformancefunctions,eliminateor
ments but they need not conform with its recommendations.
minimize the possibility of nuclear criticality and provide for
3.2 Definitions of Terms Specific to This Standard:
the protection of both the operator personnel and the public at
3.2.1 accident—an unplanned event that could result in
large under normal and abnormal (emergency) operating con-
unacceptable levels of any of the following:
ditions as well as under credible failure or accident conditions.
3.2.1.1 equipment damage,
3.2.1.2 injury to personnel,
5. General Requirements
3.2.1.3 downtime or outage,
3.2.1.4 release of hazardous materials (radioactive or non- 5.1 Basic Data and Design Criteria—The fundamental data
radioactive). and design criteria that form the basis for facilities design shall
3.2.1.5 radiation exposure to personnel, and be documented in an early stage such that evolving plant
3.2.1.6 criticality. concepts and engineering calculations have a solid and trace-
3.2.2 accountability—the keeping of records on and the able origin or foundation. Design criteria can be included in an
responsibility associated with being accountable for the owner/clientprepareddatadocumentor,whentheowner/client
amount of fissile materials entering and leaving a plant, a so instructs, they may be selected or developed by the
location, or a processing step. responsible design, organization. Values, formulas, equations,
3.2.3 basic data—the fundamental chemical, physical, and andotherdatashouldderivefromprovenandscientificallyand
mathematical values, formulas, and principles, and the defini- technically sound sources. Any and all changes to the basic
data shall be documented and dated. Procedural requirements
associated with the authentication, documentation, and reten-
AvailablefromAmericanNuclearSociety,555fN.KensingtonAve.,LaGrange
tion of the data base should be essentially equivalent to, and
Park, IL 60526.
Available from U.S. Government Printing Office, Washington, DC 20402. meet the intent of, ASME NQA-1.
C1062
5.2 Responsibility for Basic Data—The production, authen- 6.1.1 General considerations and accepted good practice in
tication, and issue of the basic data document should be the regard to the design of dissolvers and other processing vessels
responsibility of the owner/client. However, this responsibility for nuclear and radioactive materials is contained in guide
may be delegated. C 1217.
5.2.1 The Architect-Engineering (AE) organization charged 6.1.2 Design of dissolution equipment and facilities shall
with design and engineering responsibility for the nuclear fuel include provisions to minimize the release of radioactive
dissolution facilities is generally held responsible for the material from process vessels and equipment (including pipes
adequacy, appropriateness, and completeness of the basic data. or lines connecting to vessels or areas that are not normally
The AE shall indicate the acceptance of this responsibility by contaminated with radioactive material, such as cold reagent
a signed client/AE acceptance document in testimony thereof. and instrument air) or confinement (e.g. shielding cell walls)
Such an acceptance document should be executed within 90 during normal and foreseeable abnormal conditions of opera-
days after receipt of the basic data document. tion, maintenance, and decontamination.
5.3 Quality Assurance—A formalized quality assurance 6.1.3 Offgas, vapor, droplet, and foaming disengagement
program shall be conducted as required by 10 CFR 50,App B. space, equivalent to approximately 100 % freeboard should be
This program shall be in general accordance with ASME included in sizing the dissolver. The dissolver fuel baskets
NQA-1. should be sized so that the fuel charge occupies no more than
5.4 Personnel—Personnel associated with facility design 75 % of the basket depth. This will help to ensure confinement
and construction should collectively have the training, experi- of hulls and metal fragments during the dissolution cycle. Fuel
ence, and competence to understand, analyze, engineer, and basket perforations (openings) should be limited in size to
resolve questions or problems associated with their assigned retain metal fragments and yet allow free flow of dissolvent
tasks. solutions.
5.4.1 Records shall be kept showing names and responsi- 6.1.4 Design should specify the controls and checks that are
bilities of personnel involved with and responsible for the required to ensure that vessel design dimensions are achieved
design, fabrication, inspection, and installation of nuclear fuel and maintained during fabrication and construction sequences.
dissolving facilities for purposes of auditing quality assurance This is a requirement for vessels designed to provide geometri-
(QA) records. cally favorable handling conditions for fissile materials.
5.5 Degree of Quality—The quality and integrity of mate- 6.1.5 Criticality assessment calculations (see 8.1) shall in-
rials and workmanship associated with the design, fabrication, clude an allowance to compensate for vessel fabrication
and installation of nuclear fuels dissolution facilities shall be inaccuracies and corrosion. This compensatory calculation
commensurate with calculated, demonstrable needs. Such allowance is not to be construed as establishing or altering
needs arise from known and perceived risks, given physical given dimensions or tolerances on design drawings.
and chemical principles, and applicable codes and regulations. 6.1.6 The layout and installation of equipment and piping
5.5.1 In setting forth the need for any given level of quality fortheprocessingandtransferofaqueoussolutionsofenriched
or integrity, the organization or individual responsible for uranyl nitrate should be in accordance with the requirements
making any such determination shall document the tests and and constraints set forth in ANSI/ANS 8.9.
acceptance criteria by which attainment or conformity is to be 6.1.7 A gas sparge connection should be included in the
judged. Attainment or conformity verification requiremen
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