ANSI ANS 8.17-2004 Criticality Safety Criteria for the Handling Storage and Transportation of LWR Fuel Outside Reactors《反应堆外部的轻水反应堆燃料的搬运 贮藏和运输临界安全性准则》.pdf

《ANSI ANS 8.17-2004 Criticality Safety Criteria for the Handling Storage and Transportation of LWR Fuel Outside Reactors《反应堆外部的轻水反应堆燃料的搬运 贮藏和运输临界安全性准则》.pdf》由会员分享，可在线阅读，更多相关《ANSI ANS 8.17-2004 Criticality Safety Criteria for the Handling Storage and Transportation of LWR Fuel Outside Reactors《反应堆外部的轻水反应堆燃料的搬运 贮藏和运输临界安全性准则》.pdf（11页珍藏版）》请在麦多课文档分享上搜索。

1、ANSI/ANS-8.17-2004criticality safety criteria for the handling, storage,and transportation of LWR fuel outside reactorsANSI/ANS-8.17-2004This standard has been reviewed and reaffirmed with the recognition that it may reference other standards and documents that may have been superseded or withdrawn.

2、 The requirements of this document will be met by using the version of the standards and documents referenced herein. It is the responsibility of the user to review each of the references and to determine whether the use of the original references or more recent versions is appropriate for the facil

3、ity. Variations from the standards and documents referenced in this standard should be evaluated and documented. This standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance. Users should consider the use of these

4、industry initiatives in the application of this standard. REAFFIRMED September 14, 2009 ANSI/ANS-8.17-2004 (R2009) ANSI/ANS-8.17-2004American National StandardCriticality Safety Criteria for the Handling, Storage,and Transportation of LWR Fuel Outside ReactorsSecretariatAmerican Nuclear SocietyPrepa

5、red by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-8.17Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved November 3, 2004by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this docume

6、nt as an American National Standard attests thatthe principles of openness and due process have been followed in the approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under procedures of the Standards Committ

7、ee ofthe American Nuclear Society; these procedures are accredited by the Amer-ican National Standards Institute, Inc., as meeting the criteria for AmericanNational Standards. The consensus committee that approved the standardwas balanced to ensure that competent, concerned, and varied interests hav

8、ehad an opportunity to participate.An American National Standard is intended to aid industry, consumers, gov-ernmental agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notpreclude anyone from manufacturing, ma

9、rketing, purchasing, or using prod-ucts, processes, or procedures not conforming to the standard.By publication of this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The content of this standard reflects

10、acceptable practice at the time ofits approval and publication. Changes, if any, occurring through developmentsin the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany time in accordance with establishe

11、d procedures. Users of this standardare cautioned to determine the validity of copies in their possession and toestablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individual or by any ad hoc group of indi

12、viduals.Requests for interpretation should be sent to the Standards Department atSociety Headquarters. Action will be taken to provide appropriate response inaccordance with established procedures that ensure consensus on theinterpretation.Comments on this standard are encouraged and should be sent

13、to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2004 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS

14、-8.17-2004 with permission of the publisher,the American Nuclear Society.” Reproduction prohibited under copyright conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis foreword is not a part of American National Standard C

15、riticality Safety Criteria forthe Handling, Storage, and Transportation of LWR Fuel Outside Reactors, ANSI0ANS-8.17-2004!Criticality safety is an important component in a comprehensive safety assess-ment of a facility or an operation involving fissile materials. Designers, opera-tors, and standards

16、writing groups having concern with nonreactor nuclearfacilities justifiably have occasion to address criticality safety. The presentwork was undertaken in the interest of an orderly presentation that embodiescriticality safety principles and practices consistent with existing AmericanNuclear Society

17、 standards in the field of criticality safety, Subcommittee 8,Fissionable Materials Outside Reactors, of the ANS Standards Committee. Theprincipal intent of the ANS-8.17 working group has been to provide basicrequirements that address the criticality safety aspects of a facility or opera-tion and th

18、at can be referenced or used in conjunction with other safetystandards or regulations to address the total safety and operational require-ments. This standard presents safety criteria applicable to the handling, stor-age, and transportation of light water reactor fuel rods and elements outside areac

19、tor core.This revision of the standard was drafted by Working Group ANS-8.17 of Sub-committee 8 of the American Nuclear Society. The following members partici-pated in the preparation:B. O. Kidd Chair!, BWX Technologies, Inc.D. B. Lancaster, NuclearCC. D. Manning, Framatome ANPC. V. Parks, Oak Ridge

20、 National LaboratoryS. E. Turner, Holtec InternationalThe membership of Subcommittee 8, Fissionable Materials Outside Reactors, atthe time of draft preparation and approval was the following:T. P. McLaughlin Chair!, Los Alamos National LaboratoryJ. A. Schlesser Secretary!, Westinghouse Safety Manage

21、ment Solutions, LLCF. M. Alcorn, IndividualE. D. Clayton, IndividualA. S. Garcia, U.S. Department of EnergyC. M. Hopper, Oak Ridge National LaboratoryN. Ketzlach, IndividualR. Kiyose, IndividualR. A. Libby, Pacific Northwest National LaboratoryW. G. Morrison, IndividualD. A. Reed, Oak Ridge National

22、 LaboratoryT. A. Reilly, Westinghouse Safety Management Solutions, LLCP. R. Thorne, BNFLH. Toffer, Fluor Federal ServicesG. E. Whitesides, IndividualThe American National Standards Committee N16, Nuclear Criticality Safety,which reviewed and approved this standard in 2004, had the followingmembershi

23、p:C. M. Hopper Chair!, Oak Ridge National LaboratoryR. Knief Vice-Chair!, Sandia National LaboratoriesG. H. Bidinger, IndividualR. D. Busch, University of New MexicoM. S. Chatterton, U.S. Nuclear Regulatory CommissionR. S. Eby, American Institute of Chemical EngineersC. D. Manning, Framatome ANPB. M

24、cLeod, Institute of Nuclear Materials ManagementS. P. Murray, Health Physics SocietyiR. L. Reed, Washington Safety Management Solutions, LLCB. Rothleder, U.S. Department of EnergyF. W. Sanders, IndividualD. R. Smith, IndividualR. G. Taylor, IndividualJ. T. Thomas, IndividualR. M. Westfall, Oak Ridge

25、 National LaboratoryiiContentsSection Page1 Introduction . 12 Scope . 13 Definitions 14 General Safety Criteria 15 Criteria to Establish Subcriticality 26 References 3AppendixFuel Unit Handling, Storage, and Transportation: Criticality SafetyConsiderations 4 iii Criticality Safety Criteria forthe Ha

26、ndling, Storage, andTransportation of LWR FuelOutside Reactors1 IntroductionThe potential for criticality accidents during thehandling, storage, and transportation of fuel fornuclear reactors represents a health and safetyrisk to personnel involved in these activities, aswell as to the general publi

27、c. Appropriate de-sign of equipment and facilities, handling pro-cedures, and personnel training can minimizethis risk. WhileAmerican National Standard “Nu-clear Criticality Safety in Operations with Fis-sionable Materials Outside Reactors,” ANSI0ANS-8.1-19981#,1!provides general criteria forassuran

28、ce of criticality safety, this standard pro-vides additional guidance applicable to han-dling, storage, and transportation of light waterreactorLWR!nuclear fuel units in any phase ofthe fuel cycle outside the reactor core.2 ScopeThis standard provides nuclear criticality safetycriteria for the handl

29、ing, storage, and transpor-tation of LWR fuel rods and units outside reac-tor cores.3 Definitions3.1 LimitationsThe definitions given below are of a restrictednature for the purpose of this standard. Otherspecialized terms are defined in Glossary ofTerms in Nuclear Science and Technology 2#.3.2 Shal

30、l, Should, and MayThe word “shall” is used to denote a require-ment; the word “should” is used to denote arecommendation; and the word “may” is usedto denote permission, neither a requirementnor a recommendation. In order to conform withthis standard, all operations shall be per-formed in accordance

31、 with its requirements butnot necessarily with its recommendations. Whenrecommendations are not implemented, justifi-cation should be documented.3.3 Glossary of Termscontrolled parameter: A parameter that iskept within specified limits.fuel rod: A long slender column of materialcontaining fissile nu

32、clides, normally encapsu-lated by metallic tubing.fuel unit: The fundamental item to be han-dled, stored, or transported. Examples includean assembly of fuel rods, canned spent fuel, orconsolidated fuel rods.independent assessment: A review of a crit-icality safety evaluation by a competent indi-vid

33、uals!, other than the originator, thatconfirms the adequacy of the evaluation. Thereviewers! may be from the same organiza-tion as the originator.4 General Safety Criteria4.1 General administrative and technical prac-tices are contained in American National Stan-dards ANSI0ANS-8.1-1998 1# and ANSI0A

34、NS-8.19-1996 3#.4.2 Methods used to calculate the effectivemultiplication factor shall be validated in ac-cordance with ANSI0ANS-8.1-1998 1#.4.3 Guidance to determine the need for anduse of criticality alarms for personnel protec-tion is contained in American National Stan-dard “Criticality Accident

35、 Alarm System,” ANSI0ANS-8.3-1997 4#.1!Numbers in brackets refer to corresponding numbers in Section 6, “References.”14.4 Prior to first use of, or before implement-ing changes to, any operation or system involv-ing handling, storage, or transportation of fuelunits or rods, a criticality safety eval

36、uation shallbe performed for all normal and credible abnor-mal conditions2!to determine that the entireoperation or system will be subcritical basedon the criteria contained in section 5.4.5 The criticality safety evaluation shall de-termine and explicitly identify the controlledparameters and their

37、 associated design and op-erating limits upon which nuclear criticalitysafety depends. The effect of changes in theseparameters, or in the conditions to which theyapply, shall be documented.4.6 The criticality safety evaluation shall bedocumented with sufficient detail, clarity, andlack of ambiguity

38、 to allow independent reviewand confirmation of results.4.7 Prior to commencing an operation, thereshall be an independent assessment that con-firms the adequacy of the evaluation requiredby 4.4.4.8 Prior to commencing operation, the oper-ating organization shall verify that the config-urations and

39、conditions at the time of operationconform with the design and operating limitsspecified in 4.5.4.9 Reliance may be placed on neutron-absorbing materials, such as gadolinium andboron, that are incorporated in the fuel mate-rial itself, incorporated in structures or equip-ment, or included within sol

40、utions integral tothe structures or equipment. However, whenreliance is placed on neutron-absorbing mate-rials, control shall be exercised to ensure theircontinued presence with the intended configu-rations, distributions, and concentrations. Ex-traordinary care should be taken with solutionsof abso

41、rbers because of the difficulty of exer-cising such control and with fuel units contain-ing burnable poison to identify the maximumreactivity condition to be considered. Guidancefor the use of fixed neutron absorbers is con-tained in American National Standard ANSI0ANS-8.21-1995 5# and for the use o

42、f solubleneutron absorbers is contained in American Na-tional Standard ANSI0ANS-8.14-2004 6#.4.10 In performing the criticality safety eval-uation, the fuel characteristicse.g., material com-positions, geometry, temperature! that affectreactivity shall be chosen from the range of cred-ible values su

43、ch that the maximum neutronmultiplication factor of the system is obtained.Credit may be taken for fuel burnup by estab-lishing a maximum fuel unit reactivity and as-suring that each fuel unit has a reactivity nogreater than the maximum established reactiv-ity. Assurance that the reactivity limit is

44、 not ex-ceeded may be provided by 1! a measurementthat can be related to the reactivity or2!an analy-sis and verification of the exposure history of eachfuel unit. Consideration shall be given to the ax-ial distribution of burnup in the fuel unit.4.11 The fuel unit and fuel rods should behandled, st

45、ored, and transported in a mannerproviding a sufficient factor of safety to requireat least two unlikely, independent, and concur-rent changes in conditions before a criticalityaccident is possible.5 Criteria to EstablishSubcriticality5.1 Where methods of analysis are used topredict neutron multipli

46、cation factors, the cal-culated multiplication factor kpshall be equalto or less than an established allowable neu-tron multiplication factor; i.e.,kpH11349 kcH11002H9004kpH11002H9004kcH11002H9004km,where:kpis the calculated multiplication factorkeffof the system being evaluated forall normal or cre

47、dible abnormal condi-tions or events;kcis the mean keffthat results from thecalculation of the benchmark criticalityexperiments using a particular calcula-tional method. The criticality experi-ments used as benchmarks in computingkcshould have physical compositions,configurations, and nuclear charac

48、ter-istics including reflectors! similar tothose of the system being evaluated. Ifthe system being evaluated has param-2!Examples of conditions that may be appropriate for consideration are given in the Appendix.American National Standard ANSI0ANS-8.17-20042eters! beyond the area of applicabilityest

49、ablished by the benchmark critical-ity experiments, then the area of appli-cability may be extended by using trendsin the calculated values of kcwith theparameters!. For large extensions, theuse of trends should be supplementedby use of other calculational methods.See ANSI0ANS-8.1-1998 1# for furtherguidance on the area of applicabilityand extension beyond the area of ap-plicability.3!H9004kpis an allowance forstatistical or convergence uncertain-ties, or both, in the computation ofkp;material and fabrication tolerances;uncertainties due to lim