1、Designation: C 1062 00 (Reapproved 2008)Standard Guide forDesign, Fabrication, and Installation of Nuclear FuelDissolution Facilities1This standard is issued under the fixed designation C 1062; the number immediately following the designation indicates the year oforiginal adoption or, in the case of
2、 revision, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 It is the intent of this guide to set forth criteria andprocedures for the design, fabrication
3、and installation ofnuclear fuel dissolution facilities. This guide applies to andencompasses all processing steps or operations beyond the fuelshearing operation (not covered), up to and including thedissolving accountability vessel.1.2 Applicability and Exclusions:1.2.1 OperationsThis guide does no
4、t cover the operationof nuclear fuel dissolution facilities. Some operating consider-ations are noted to the extent that these impact upon orinfluence design.1.2.1.1 Dissolution ProceduresFuel compositions, fuelelement geometry, and fuel manufacturing methods are subjectto continuous change in respo
5、nse to the demands of newreactor designs and requirements. These changes preclude theinclusion of design considerations for dissolvers suitable forthe processing of all possible fuel types. This guide will onlyaddress equipment associated with dissolution cycles for thosefuels that have been used mo
6、st extensively in reactors as of thetime of issue (or revision) of this guide. (See Appendix X1.)1.2.2 ProcessesThis guide covers the design, fabricationand installation of nuclear fuel dissolution facilities for fuels ofthe type currently used in Pressurized Water Reactors (PWR).Boiling Water React
7、ors (BWR), Pressurized Heavy WaterReactors (PHWR) and Heavy Water Reactors (HWR) and thefuel dissolution processing technologies discussed herein.However, much of the information and criteria presented maybe applicable to the equipment for other dissolution processessuch as for enriched uranium-alum
8、inum fuels from typicalresearch reactors, as well as for dissolution processes for somethorium and plutonium-containing fuels and others. The guidedoes not address equipment design for the dissolution of highburn-up or mixed oxide fuels.1.2.2.1 This guide does not address special dissolutionprocesse
9、s that may require substantially different equipment orpose different hazards than those associated with the fuel typesnoted above. Examples of precluded cases are electrolyticdissolution and sodium-bonded fuels processing. The guidedoes not address the design and fabrication of continuousdissolvers
10、.1.2.3 Ancillary or auxiliary facilities (for example, steam,cooling water, electrical services) are not covered. Cold chemi-cal feed considerations are addressed briefly.1.2.4 Dissolution PretreatmentFuel pretreatment steps in-cidental to the preparation of spent fuel assemblies for disso-lution re
11、processing are not covered by this guide. This exclu-sion applies to thermal treatment steps such as “Voloxidation”to drive off gases prior to dissolution, to mechanical decladdingoperations or process steps associated with fuel elementsdisassembly and removal of end fittings, to chopping andshearin
12、g operations, and to any other pretreatment operationsjudged essential to an efficient nuclear fuels dissolution step.1.2.5 FundamentalsThis guide does not address specificchemical, physical or mechanical technology, fluid mechanics,stress analysis or other engineering fundamentals that are alsoappl
13、ied in the creation of a safe design for nuclear fueldissolution facilities.1.3 The values stated in inch-pound units are to be regardedas standard. The values given in parentheses are mathematicalconversions to SI units that are provided for information onlyand are not considered standard.1.4 This
14、standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2
15、.1 Industry and National Consensus StandardsIndustryand national consensus standards applicable in whole or in partto the design, fabrication, and installation of nuclear fueldissolution facilities are referenced throughout this guide andinclude the following:2.2 ASTM Standards:21This guide is under
16、 the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved June 1, 2008. Published July 2008. Originally approvedin 1986. Last previous edition approved in 2000 as C 1062 00.2For referenced ASTM s
17、tandards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocke
18、n, PA 19428-2959, United States.C 1010 Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels ReprocessingFacility3C 1217 Guide for Design of Equipment for ProcessingNuclear and Radioactive Materials2.3 ASME Standards:4ASME Boiler and Pressure Vessel Code, Sections II, V,VIII
19、, and IXASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications2.4 ANS Standard:5ANS Glossary of Terms in Nuclear Science and Technology(ANS Glossary)ANS 8.1 Nuclear Criticality Safety in Operations withFissionable Materials Outside ReactorsANS 8.3 Criticality Accident Alarm Syste
20、mANS 8.9 Nuclear Criticality Safety Criteria for Steel-PipeIntersections Containing Aqueous Solutions of FissileMaterialsANS 57.8 Fuel Assembly Identification2.5 Federal Regulations6Federal Regulations that arespecifically applicable in whole or in part to the design,fabrication, and installation of
21、 nuclear fuel dissolution facilitiesinclude the following:10CFR50 Licensing of Production and Utilization Facilities10CFR50, App B Quality Assurance Criteria for NuclearPower Plants and Fuel Reprocessing Plants2.6 This guide does not purport to list all standards, codes,and/or federal regulations th
22、at may apply to nuclear fueldissolution facilities design.3. Terminology3.1 General:3.1.1 The terminology used in this guide is intended toconform with industry practice insofar as is practicable, but thefollowing terms are of a restricted nature, specifically appli-cable to this guide. Other terms
23、and their definitions arecontained in the ANS Glossary.3.1.2 shall, should, and mayThe word “shall” denotes arequirement, the word “should” denotes a recommendation andthe word “may” indicates permission, neither a requirementnor a recommendation. In order to conform with this guide, allactions or c
24、onditions shall be in accordance with its require-ments but they need not conform with its recommendations.3.2 Definitions of Terms Specific to This Standard:3.2.1 accidentan unplanned event that could result inunacceptable levels of any of the following:3.2.1.1 equipment damage,3.2.1.2 injury to pe
25、rsonnel,3.2.1.3 downtime or outage,3.2.1.4 release of hazardous materials (radioactive or non-radioactive).3.2.1.5 radiation exposure to personnel, and3.2.1.6 criticality.3.2.2 accountabilitythe keeping of records on and theresponsibility associated with being accountable for theamount of fissile ma
26、terials entering and leaving a plant, alocation, or a processing step.3.2.3 basic datathe fundamental chemical, physical, andmathematical values, formulas, and principles, and the defini-tive criteria that have been documented and accepted as thebasis for facilities design.3.2.4 double contingency p
27、rinciplethe use of methods,measures, or factors of safety in the design of nuclear facilitiessuch that at least two unlikely, independent, and concurrentchanges in process or operating conditions are required beforea criticality accident is possible.3.2.5 eructationa surface eruption in a tank, vess
28、el, orliquefied pool caused by the spontaneous release of gas orvapor, or both, from within the liquid. An eructation may bearsome resemblance to the flashing of superheated water; but itbest resembles a burping action that may or may not beaccompanied by dispersion of liquid droplets or particulate
29、s, orboth, and by a variable degree of liquid splashing. Thepotential for eructation is most often caused by an excessiveheating rate combined with an inadequate agitation condition.3.2.6 geometrically favorablea term applied to a vessel orsystem having dimensions and a shape or configuration thatpr
30、ovides assurance that a criticality incident cannot occur in thevessel or system under a given set of conditions. The givenconditions require that the isotopic composition, form, concen-tration, and density of fissile materials in the system willduplicate those used in preparation of the criticality
31、 analysis.These variables will remain within conservatively chosenlimits, and moderator and reflector conditions will be withinsome permitted range.3.2.7 poison or poisonedany material used to minimizethe potential for criticality, usually containing quantities of oneof the chemical elements having
32、a high neutron absorptioncross-section, for example, boron, cadmium, gadolinium, etc.4. Significance and Use4.1 The purpose of this guide is to provide information thatwill help to ensure that nuclear fuel dissolution facilities areconceived, designed, fabricated, constructed, and installed inan eco
33、nomic and efficient manner. This guide will helpfacilities meet the intended performance functions, eliminate orminimize the possibility of nuclear criticality and provide forthe protection of both the operator personnel and the public atlarge under normal and abnormal (emergency) operating con-diti
34、ons as well as under credible failure or accident conditions.5. General Requirements5.1 Basic Data and Design CriteriaThe fundamental dataand design criteria that form the basis for facilities design shallbe documented in an early stage such that evolving plantconcepts and engineering calculations h
35、ave a solid and trace-able origin or foundation. Design criteria can be included in an3Withdrawn.4Available from American Society of Mechanical Engineers (ASME), ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990, http:/www.asme.org.5Available fromAmerican Nuclear Society, 555f
36、 N. KensingtonAve., La GrangePark, IL 60526.6Available 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.C 1062 00 (2008)2owner/client prepared data document or, when the owner/clientso instructs, t
37、hey may be selected or developed by theresponsible design, organization. Values, formulas, equations,and other data should derive from proven and scientifically andtechnically sound sources. Any and all changes to the basicdata shall be documented and dated. Procedural requirementsassociated with th
38、e authentication, documentation, and reten-tion of the data base should be essentially equivalent to, andmeet the intent of, ASME NQA-1.5.2 Responsibility for Basic DataThe production, authen-tication, and issue of the basic data document should be theresponsibility of the owner/client. However, thi
39、s responsibilitymay be delegated.5.2.1 The Architect-Engineering (AE) organization chargedwith design and engineering responsibility for the nuclear fueldissolution facilities is generally held responsible for theadequacy, appropriateness, and completeness of the basic data.The AE shall indicate the
40、 acceptance of this responsibility bya signed client/AE acceptance document in testimony thereof.Such an acceptance document should be executed within 90days after receipt of the basic data document.5.3 Quality AssuranceA formalized quality assuranceprogram shall be conducted as required by 10 CFR 5
41、0, App B.This program shall be in general accordance with ASMENQA-1.5.4 PersonnelPersonnel associated with facility designand construction should collectively have the training, experi-ence, and competence to understand, analyze, engineer, andresolve questions or problems associated with their assig
42、nedtasks.5.4.1 Records shall be kept showing names and responsi-bilities of personnel involved with and responsible for thedesign, fabrication, inspection, and installation of nuclear fueldissolving facilities for purposes of auditing quality assurance(QA) records.5.5 Degree of QualityThe quality an
43、d integrity of mate-rials and workmanship associated with the design, fabrication,and installation of nuclear fuels dissolution facilities shall becommensurate with calculated, demonstrable needs. Suchneeds arise from known and perceived risks, given physicaland chemical principles, and applicable c
44、odes and regulations.5.5.1 In setting forth the need for any given level of qualityor integrity, the organization or individual responsible formaking any such determination shall document the tests andacceptance criteria by which attainment or conformity is to bejudged. Attainment or conformity veri
45、fication requirementsshould be written into the Quality Assurance Inspection pro-cedures.5.6 Records RetentionAll records pertaining to the basicdata, design calculations, computer analysis, quality, qualityassurance, chemical or physical test results, inspections, andother records that bear on the
46、condition, safety, or integrity ofthe dissolution system facilities shall be available for auditpurposes at any time subsequent to their creation.6. Equipment6.1 Design ConsiderationsThe general principles used todesign dissolvers for nuclear fuels are essentially the same asthose widely employed in
47、 the design of processing equipmentin the chemical industry. Design of nuclear processing facilitiespresents three additional considerations: the possibility ofnuclear criticality, the dissipation of heat created by radioactivedecay, and the provision for the adequate containment ofradioactive conta
48、minants under both normal and abnormalconditions. The latter consideration demands a degree ofquality and the application of quality assurance procedures thatare in excess of those that are normally required in thechemical industry.6.1.1 General considerations and accepted good practice inregard to
49、the design of dissolvers and other processing vesselsfor nuclear and radioactive materials is contained in guideC 1217.6.1.2 Design of dissolution equipment and facilities shallinclude provisions to minimize the release of radioactivematerial from process vessels and equipment (including pipesor lines connecting to vessels or areas that are not normallycontaminated with radioactive material, such as cold reagentand instrument air) or confinement (for example, shielding cellwalls) during normal and foreseeable abnormal conditions ofoperation, maintenance, and
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