ASTM C1062-2000 Standard Guide for Design Fabrication and Installation of Nuclear Fuel Dissolution Facilities《核燃料溶解装置的设计、制造和安装标准指南》.pdf

《ASTM C1062-2000 Standard Guide for Design Fabrication and Installation of Nuclear Fuel Dissolution Facilities《核燃料溶解装置的设计、制造和安装标准指南》.pdf》由会员分享，可在线阅读，更多相关《ASTM C1062-2000 Standard Guide for Design Fabrication and Installation of Nuclear Fuel Dissolution Facilities《核燃料溶解装置的设计、制造和安装标准指南》.pdf（17页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C 1062 00Standard 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 revision, the yea

2、r of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) 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 and installation

3、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 cover the opera

4、tionof 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 response to the demand

5、s 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 most extensively in

6、 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 Reactors (BWR), Pressu

7、rized 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-aluminum fuels from t

8、ypicalresearch 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 dissolutionprocesses that may requir

9、e 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.1.2.3 Ancillary

10、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 reprocessing are no

11、t 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 andshearing operations, and

12、 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 alsoapplied in the creati

13、on of a safe design for nuclear fueldissolution facilities.1.3 This 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-bi

14、lity of regulatory limitations prior to use.2. Referenced Documents2.1 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 gui

15、de andinclude the following:2.2 ASTM Standards:2C 1010 Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels ReprocessingFacilityC 1217 Guide for Design of Equipment for ProcessingNuclear and Radioactive Materials2.3 ASME Standards:3ASME Boiler and Pressure Vessel Code, Sect

16、ions II, V,VIII, and IX1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved June 10, 2000. Published August 2000.2Annual Book of ASTM Standards, Vol 12.01.3Available from

17、 American Society of Mechanical Engineers, 3 Park Ave., NewYork, NY 10016.1Copyright ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.ASME NQA-1 Quality Assurance Requirements forNuclear Facility Applications2.4 ANS Standard:4ANS Glossary of Terms in Nuclear Science and T

18、echnology(ANS Glossary)ANS 8.1 Nuclear Criticality Safety in Operations withFissionable 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 Id

19、entification2.5 Federal Regulations5Federal Regulations that arespecifically applicable in whole or in part to the design,fabrication, and installation of nuclear fuel dissolution facilitiesinclude the following:10CFR50 Licensing of Production and Utilization Facilities10CFR50, App B Quality Assuran

20、ce Criteria for NuclearPower Plants and Fuel Reprocessing Plants2.6 This guide does not purport to list all standards, codes,and/or federal regulations that may apply to nuclear fueldissolution facilities design.3. Terminology3.1 General:3.1.1 The terminology used in this guide is intended toconform

21、 with industry practice 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” denote

22、s a recommendation andthe 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 Th

23、is 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 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

24、, and3.2.1.6 criticality.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,

25、formulas, and principles, 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 con

26、currentchanges in process 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

27、the flashing of superheated 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 wit

28、h an inadequate agitation 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

29、 the isotopic composition, form, concen-tration, 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 rang

30、e.3.2.7 poison or poisonedany 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 pr

31、ovide information thatwill 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 nuclea

32、r criticality and provide 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.5. General Requirements5.1 Basic Data and Design CriteriaThe fundamental dataand desi

33、gn 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-able origin or foundation. Design criteria can be included in anowner/client prepared data document or, when the owner/clien

34、tso instructs, they 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 requirementsas

35、sociated 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 Basic DataThe production, authen-tication, and issue of the basic data document should be theresponsibility of the owner/clie

36、nt. However, this responsibilitymay be delegated.4Available from American Nuclear Society, 555f N. Kensington Ave., La GrangePark, IL 60526.5Available from U.S. Government Printing Office, Washington, DC 20402.C 106225.2.1 The Architect-Engineering (AE) organization chargedwith design and engineerin

37、g responsibility for the nuclear fueldissolution 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

38、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 50, App B.This program shall be in general accordance with ASMENQA-1.5.4 PersonnelPersonnel associated with facility

39、designand construction should collectively have the training, experi-ence, and competence to understand, analyze, engineer, andresolve questions or problems associated with their assignedtasks.5.4.1 Records shall be kept showing names and responsi-bilities of personnel involved with and responsible

40、for thedesign, fabrication, inspection, and installation of nuclear fueldissolving facilities for purposes of auditing quality assurance(QA) records.5.5 Degree of QualityThe quality and integrity of mate-rials and workmanship associated with the design, fabrication,and installation of nuclear fuels

41、dissolution facilities shall becommensurate 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

42、 individual responsible formaking any such determination 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 re

43、cords pertaining to the basicdata, design calculations, 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

44、 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 the design of processing equipmentin the chemical industry. Design of nuclear processing facilitiespresents three a

45、dditional considerations: the possibility ofnuclear 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 applic

46、ation 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 the design of dissolvers and other processing vesselsfor nuclear and radioactive materials is contained in guideC 12

47、17.6.1.2 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 reagenta

48、nd instrument air) or confinement (e.g. shielding cell walls)during normal and foreseeable abnormal conditions of opera-tion, maintenance, and decontamination.6.1.3 Offgas, vapor, droplet, and foaming disengagementspace, equivalent to approximately 100 % freeboard should beincluded in sizing the dis

49、solver. The dissolver fuel basketsshould be sized so that the fuel charge occupies no more than75 % of the basket depth. This will help to ensure confinementof hulls and metal fragments during the dissolution cycle. Fuelbasket perforations (openings) should be limited in size toretain metal fragments and yet allow free flow of dissolventsolutions.6.1.4 Design should specify the controls and checks that arerequired to ensure that vessel design dimensions are achievedand maintained during fabrication and construction sequences.This is a requirement for vessels designed