ANS 19 6 1-2011 reload startup physics tests for pressurized water reactors《压水堆重新装料起动的物理试验》.pdf

《ANS 19 6 1-2011 reload startup physics tests for pressurized water reactors《压水堆重新装料起动的物理试验》.pdf》由会员分享，可在线阅读，更多相关《ANS 19 6 1-2011 reload startup physics tests for pressurized water reactors《压水堆重新装料起动的物理试验》.pdf（33页珍藏版）》请在麦多课文档分享上搜索。

1、ANSI/ANS-19.6.1-2011reload startup physics testsfor pressurized water reactorsANSI/ANS-19.6.1-2011ANSI/ANS-19.6.1-2011American National StandardReload Startup Physics Testsfor Pressurized Water ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorki

2、ng Group ANS-19.6.1Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved January 13, 2011by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe prin

3、ciples 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 Committee ofthe American Nuclear Society; these procedures are

4、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 havehad an opportunity to participate.An American National

5、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, marketing, purchasing, or using prod-ucts, processes, or p

6、rocedures 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 acceptable practice at the time ofits approval and publi

7、cation. 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 It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures. Users of this standardare cautioned to det

8、ermine 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 individuals.Requests for interpretation should be sent to th

9、e 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 to SocietyHeadquarters.Published byAmerican Nuclear Soci

10、ety555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2011 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-19.6.1-2011 with permission of the publisher,the Americ

11、an 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 “Reload Startup PhysicsTests for Pressurized Water Reac

12、tors,” ANSI0ANS-19.6.1-2011.!It is the intent of this American National Standard to provide guidance forverifying the nuclear characteristics of a commercial pressurized water reactorcore. This standard is intended to cover the physics tests that are performedfollowing a refueling or other alteratio

13、n of the reactor core for which nucleardesign calculations are required. This standard provides the minimum accept-able startup physics test program; however, the standard recognizes that addi-tional tests may be required by special design features for a particular core. Thisstandard does not reflec

14、t all test programs that have been approved by the U.S.Nuclear Regulatory Commission. This standard specifies the minimum testingrequired to confirm that the reconstructed core is the same as the designed core.Compliance with the intent of this standard can be demonstrated by meeting thefollowing re

15、quirements:1! Perform the physics tests described herein using an acceptable test method;2! Determine if the test results agree with the predicted results within thepreviously established test criteria;3! Document the above in accordance with the requirements of Sec. 7 of thisstandard.Suggestions fo

16、r the improvement of this standard are welcome. They should besent to the American Nuclear Society, 555 North Kensington Avenue, La GrangePark, Illinois 60526.Following is a summary of changes that were made to the 2005 version:1! The list of acceptable methods for each physics test has been moved t

17、o theAppendix;2! The overall bases for performing a startup test program has been added;3! The bases for performing each physics test has been added in the Appendix;4! Several clarifications and editing changes were made.This standard was developed by Working Group ANS-19.6.1 of the AmericanNuclear

18、Society, which had the active participation of the following members inpreparing the current version:C. T. Rombough Chair!, CTR Technical Services, Inc.P. D. Adam, Wolf Creek Nuclear Operating CorporationA. C. Attard, U.S. Nuclear Regulatory CommissionR. A. Borchert, Millstone Power StationJ. D. Bro

19、wn, AREVA CorporationJ. M. Dever, AREVA CorporationL. R. Grobmyer, Westinghouse Electric Corporation, LLCD. B. Kelley, First Energy Nuclear Operating CompanyD. K. Powers, Southern California EdisonG. M. Presnell, Duke Power CompanyM. C. Prible, Westinghouse Electric Corporation, LLCP. C. Rohr, Westi

20、nghouse Electric Corporation, LLCK. Sahadewan, Exelon NuclearC. P. Stafford, Arizona Public ServiceJ. D. Wade, Arizona Public ServiceD. A. Wellbaum, Catawba Nuclear StationThe membership of Subcommittee ANS-19 at the time of its review and approvalof this standard was as follows:iD. M. Cokinos Chair

21、!, Brookhaven National LaboratoryC. T. Rombough Secretary!, CTR Technical Services, Inc.A. C. Attard, U.S. Nuclear Regulatory CommissionW. H. Bell, American Institute of Chemical Engineers Representative (employed by South CarolinaElectric k2is the effective multiplication constant forreactor state

22、2.regulating control rod group: A group ofcontrol rods that may be partially or fully in-serted in the core during normal operation.safety control rod group: A control rod groupthat remains withdrawn from the core duringnormal operation also known as “shutdownrod group” or “shutdown bank”!.shall, sh

23、ould, and may: The word “shall” isused to denote a requirement; the word “should”is used to denote a recommendation; and theword “may” is used to denote permission, nei-ther a requirement nor a recommendation.test criterion: The predetermined value forevaluating the result of each test. Also knownas

24、 “review criterion.” The value is based ondifferences between calculations and measure-ments that would suggest a problem with theas-built core, the measurement, or the predic-tion. The value is not based on safety analysisassumptions. See the Appendix for a more com-plete discussion of test review!

25、 criteria used inthis standard.3!Numbers in brackets refer to corresponding numbers in Sec. 8, “References.”American National Standard ANSI0ANS-19.6.1-201124 Relation to other standardsAmerican National Standard ANSI0ANS-3.2-2006, “Administrative Controls and Quality As-surance for the Operational P

26、hase of NuclearPower Plantswithdrawn!”2#, provides require-ments and recommendations for an administra-tive control and quality assurance program forthe safe and efficient operation of nuclear powerplants. Provisions for test and applicable testequipment control required by this standardare also inc

27、luded in ANSI0ANS-3.2-2006. Amer-ican National Standard ANSI0ANS-3.1-1993R1999!W2009!, “Selection, Qualification, andTraining of Personnel for Nuclear Power Plants”withdrawn!3#, provides for the selection, qual-ification, and training of personnel for nuclearpower plants, including personnel respons

28、iblefor startup testing.American National Standard ANSI0ANS-19.4-1976 R2000!W2010!, “A Guide for Acquisi-tion and Documentation of Reference PowerReactor Physics Measurements for NuclearAnaly-sis Verification” withdrawn!4#, and Ameri-can National Standard ANSI0ANS-19.5-1995W2005!, “Requirements for

29、Reference ReactorPhysics Measurements” withdrawn!5#, ad-dress reactor physics measurements that areintended to yield documented data of both thetype and quality required for validating nu-clear analysis methods. American NationalStandard ANSI0ANS-19.11-1997 R2002!, “Cal-culation and Measurement of t

30、he ModeratorTemperature Coefficient of Reactivity for Wa-ter Moderated Power Reactors” 6#, describeshow to calculate and measure the moderatortemperature coefficient of reactivity. This stan-dard, ANSI0ANS-19.6.1-2011, defines the min-imum acceptable startup physics test programand acceptable test m

31、ethods to determine ifthe reactor core operating characteristics areconsistent with the design predictions.5 Physics test program andselection criteria5.1 Bases for startup physics testprogramDuring the reload design process, the reactorsafety is determined by analysis. Following thereload, specific

32、 core characteristics shall be con-firmed by measurement to ensure that the re-constructed core is accurately represented bythat analysis and is operating as designed. Thus,the testing results seek to confirm that thereactor can be operated within the bounds ofthe technical specifications, that ther

33、e is suffi-cient operational flexibility, and that the plantcan be expected to safely deliver the designedpower output.The important analysis characteristics that shallbe confirmed by measurement are the following:1! Reactivity balance: Reactivity balance neu-tronically demonstrates that the total a

34、mountof fuel loaded in the core is consistent withdesign. The boron endpoint measurementsconfirm that the amount of various fission-able materials in the core, as well as thereactivity effects of various fixed poisonse.g.,burnable absorbers! and transient poisonse.g., samarium!, is consistent with t

35、he de-sign calculations;2! Reactivity control: Reactivity control re-fers to the reactor core parameters that havean impact on the ability of the operators tocontrol the plant. The primary parameter thatconfirms this is the isothermal temperaturecoefficient;3! Power distribution: The power distribu-

36、tion is a measurement check! that the coreis loaded properly and will perform as de-signed. When the measured power distribu-tions agree with predictions, there is highconfidence that the as-built core and the de-signed core are the same. In addition, thereis increased confidence that the conclusion

37、sof the safety analyses are correct. Finally,close agreement between measured and pre-dicted power distributions increases the con-fidence that reactivity control parameters willperform as designed;4! Capability to shutdown: Capability to shut-down is demonstrated by showing that themeasured control

38、 rod worths are consistentwith the calculated values. The shutdown mar-gin calculations are based upon design val-ues, which have to be confirmed;5! Requirements to shutdown: The require-ments to shutdown are the reactivity ele-ments that the safety and regulating controlrods have to overcome in a r

39、eactor trip. TheAmerican National Standard ANSI0ANS-19.6.1-20113shutdown margin calculations are based upondesign values, which have to be confirmed.Any new testing process or program of teststhat are not described in the Appendix of thisstandard shall specify how the above param-eters are to be con

40、firmed.The reload startup testing program is con-structed such that as the power ascension pro-ceeds, the level of confidence in confirmedreactor characteristics continues to improve.Similarly, the results of testing at a given powerlevel shall provide reasonable assurance thatthe next proposed powe

41、r level can be achievedwithout risk of violating the design or licensingbases of the plant.A minimum test program is designed to en-sure a complete certification, assuming noanomalies were identified during the test pro-gram. When results show deviations from pre-dictions that are beyond the experie

42、nce base,supplementary actions shall be identified andperformed, as necessary. A complete designverification test program should identify the min-imum testing that will be performed and the sup-plementary actions that may be performed.5.2 Required minimum test programThe characteristics required to

43、be confirmed bythis standard, example measured parametersused for confirmation, and power levels beforewhich they shall be confirmed are provided byTable 1. The parameters were selected by con-sidering the following requirements:1! The information obtained from the param-eter cannot be inferred from

44、 other tests thatwill be performed. This requirement meansthat redundant tests can be excluded. In theevent that a particular parameter fails topass the test criteria, however, other redun-dant! tests should be performed to help re-solve the discrepancy;2! Each test shall be able to quantitativelyme

45、asure an important physics characteristicof the reactor core. This requirement meansthat the following types of measurements wereexcluded although they may be performedfor other reasons!:a! mechanical tests of system compo-nents rod drop time, etc.!,b! tests used solely for instrumentcalibration,c!

46、tests used to benchmark computermodels;3! Each measurement shall be accurate, andan accurate prediction shall be available. Thisrequirement means that the expected differ-ence between the measured result and theprediction shall be small so that if the mea-surement and the prediction agree, there isc

47、onfidence that the core will behave as pre-dicted. Conversely, if there actually is a de-sign discrepancy in the core, the measurementwill reveal it the measurement and predic-tion will not agree!;4! The test program shall be designed to notviolate the plants shutdown margin require-ments. This requ

48、irement means that the plantshutdown margin requirements shall not beviolated while performing startup physicstesting.6 Test method requirementsEstablished test methods for the confirmationof each characteristic required by this stan-dard are described in the Appendix. Whetherone of these methods or

49、 a different method isused, the user shall verify that the followingrequirements are met:1! The intent, content, purpose, and otherrequirements of the overall startup programas outlined in this standard are met;2! The method unambiguously confirms oneor more of the five physics characteristicsdescribed in Sec. 5.1;3! The method has been validated by suc-cessful benchmarking;4! The method has withstood independentpeer review.6.1 General test considerations6.1.1 Test objectiveThe general objective of each test is to measurea reactor physics