1、Designation: C1062 00 (Reapproved 2014)Standard Guide forDesign, Fabrication, and Installation of Nuclear FuelDissolution Facilities1This standard is issued under the fixed designation C1062; the number immediately following the designation indicates the year oforiginal adoption or, in the case of r
2、evision, 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 an
3、d 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 not
4、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, fuel el-ement 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:1This guide is under the jurisdiction of
16、 ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved June 1, 2014. Published June 2014. Originallyapproved in 1986. Last previous edition approved in 2008 as C1062 00 (2008).DOI: 10.1520/C1062-00R14.Copyright A
17、STM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States12.2 ASTM Standards:2C1010 Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels ReprocessingFacility (Withdrawn 2001)3C1217 Guide for Design of Equipment for ProcessingNucl
18、ear and Radioactive Materials2.3 ASME Standards:4ASME Boiler and Pressure Vessel Code, Sections II, V, VIII,and IXASME NQA-1 QualityAssurance Requirements for NuclearFacility Applications2.4 ANS Standard:5ANS Glossary of Terms in Nuclear Science and Technology(ANS Glossary)ANS 8.1 Nuclear Criticalit
19、y Safety in Operations with Fis-sionable Materials Outside ReactorsANS 8.3 Criticality Accident Alarm SystemANS 8.9 Nuclear Criticality Safety Criteria for Steel-PipeIntersections Containing Aqueous Solutions of FissileMaterialsANS 57.8 Fuel Assembly Identification2.5 Federal Regulations6Federal Reg
20、ulations that arespecifically applicable in whole or in part to the design,fabrication, and installation of nuclear fuel dissolution facilitiesinclude the following:10 CFR 50 Licensing of Production and Utilization Facilities10 CFR 50, App B Quality Assurance Criteria for NuclearPower Plants and Fue
21、l Reprocessing Plants2.6 This guide does not purport to list all standards, codes,or federal regulations, or combinations thereof that may applyto nuclear fuel dissolution facilities design.3. Terminology3.1 General:3.1.1 The terminology used in this guide is intended toconform with industry practic
22、e insofar as is practicable, but thefollowing terms are of a restricted nature, specifically appli-cable to this guide. Other terms 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 and
23、the word “may” indicates permission, neither a requirementnor a recommendation. In order to conform with this guide, allactions or conditions 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 acci
24、dentan unplanned event that could result inunacceptable 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 non-radioactive).3.2.1.5 radiation exposure to personnel, and3.2.1.6 criticali
25、ty.3.2.2 accountabilitythe keeping of records on and theresponsibility associated with being accountable for theamount of fissile materials entering and leaving a plant, alocation, or a processing step.3.2.3 basic datathe fundamental chemical, physical, andmathematical values, formulas, and principl
26、es, and the defini-tive criteria that have been documented and accepted as thebasis for facilities design.3.2.4 double contingency principlethe use of methods,measures, or factors of safety in the design of nuclear facilitiessuch that at least two unlikely, independent, and concurrentchanges in proc
27、ess or operating conditions are required beforea criticality accident is possible.3.2.5 eructationa surface eruption in a tank, vessel, 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 superh
28、eated water; but itbest resembles a burping action that may or may not beaccompanied by dispersion of liquid droplets or particulates, orboth, and by a variable degree of liquid splashing. Thepotential for eructation is most often caused by an excessiveheating rate combined with an inadequate agitat
29、ion condition.3.2.6 geometrically favorablea term applied to a vessel orsystem having dimensions and a shape or configuration thatprovides assurance that a criticality incident cannot occur in thevessel or system under a given set of conditions. The givenconditions require that the isotopic composit
30、ion, form,concentration, and density of fissile materials in the system willduplicate those used in preparation of the criticality analysis.These variables will remain within conservatively chosenlimits, and moderator and reflector conditions will be withinsome permitted range.3.2.7 poison or poison
31、edany material used to minimizethe potential for criticality, usually containing quantities of oneof the chemical elements having 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 thatwi
32、ll help to ensure that nuclear fuel dissolution facilities areconceived, designed, fabricated, constructed, and installed inan economic and efficient manner. This guide will helpfacilities meet the intended performance functions, eliminate orminimize the possibility of nuclear criticality and provid
33、e forthe protection of both the operator personnel and the public atlarge under normal and abnormal (emergency) operating con-ditions as well as under credible failure or accident conditions.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serv
34、iceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3The last approved version of this historical standard is referenced onwww.astm.org.4Available from American Society of Mechanical Engineers (ASME), ASMEInternational Hea
35、dquarters, Two Park Ave., New York, NY 10016-5990, http:/www.asme.org.5Available fromAmerican Nuclear Society, 555f 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, htt
36、p:/www.access.gpo.gov.C1062 00 (2014)25. 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 have a solid and trace-a
37、ble origin or foundation. Design criteria can be included in anowner/client prepared data document or, when the owner/clientso instructs, they may be selected or developed by theresponsible design, organization. Values, formulas, equations,and other data should derive from proven and scientifically
38、andtechnically sound sources. Any and all changes to the basicdata shall be documented and dated. Procedural requirementsassociated with the 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 Ba
39、sic DataThe production,authentication, and issue of the basic data document should bethe responsibility of the owner/client. However, this responsi-bility may be delegated.5.2.1 The Architect-Engineering (AE) organization chargedwith design and engineering responsibility for the nuclear fueldissolut
40、ion facilities is generally held responsible for theadequacy, appropriateness, and completeness of the basic data.The AE shall indicate the acceptance of this responsibility bya signed client/AE acceptance document in testimony thereof.Such an acceptance document should be executed within 90days aft
41、er receipt of the basic data document.5.3 Quality AssuranceAformalized quality assurance pro-gram shall be conducted as required by 10 CFR 50, App B.This program shall be in general accordance with ASMENQA-1.5.4 PersonnelPersonnel associated with facility designand construction should collectively h
42、ave the training,experience, and competence to understand, analyze, engineer,and resolve questions or problems associated with their as-signed tasks.5.4.1 Records shall be kept showing names and responsi-bilities of personnel involved with and responsible for thedesign, fabrication, inspection, and
43、installation of nuclear fueldissolving facilities for purposes of auditing quality assurance(QA) records.5.5 Degree of QualityThe quality and integrity of materi-als and workmanship associated with the design, fabrication,and installation of nuclear fuels dissolution facilities shall becommensurate
44、with calculated, demonstrable needs. Suchneeds arise from known and perceived risks, given physicaland chemical principles, and applicable codes 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 d
45、etermination shall document the tests andacceptance criteria by which attainment or conformity is to bejudged. Attainment or conformity verification requirementsshould be written into the Quality Assurance Inspection pro-cedures.5.6 Records RetentionAll records pertaining to the basicdata, design ca
46、lculations, computer analysis, quality, qualityassurance, chemical or physical test results, inspections, andother records that bear on the condition, safety, or integrity ofthe dissolution system facilities shall be available for auditpurposes at any time subsequent to their creation.6. Equipment6.
47、1 Design ConsiderationsThe general principles used todesign dissolvers for nuclear fuels are essentially the same asthose widely employed in the design of processing equipmentin the chemical industry. Design of nuclear processing facilitiespresents three additional considerations: the possibility of
48、nuclear criticality, the dissipation of heat created by radioactivedecay, and the provision for the adequate containment ofradioactive contaminants under both normal and abnormalconditions. The latter consideration demands a degree ofquality and the application of quality assurance procedures thatar
49、e in excess of those that are normally required in thechemical industry.6.1.1 General considerations and accepted good practice inregard to the design of dissolvers and other processing vesselsfor nuclear and radioactive materials is contained in guideC1217.6.1.2 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 instrum
