ASTM E900-2015e1 1181 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials《预测在反应堆容器材料中辐射感应变化导致温度漂移的标准指南》.pdf

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1、Designation: E900 151Standard Guide forPredicting Radiation-Induced Transition Temperature Shiftin Reactor Vessel Materials1This standard is issued under the fixed designation E900; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, t

2、he 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.1NOTEOld Ref 1 was editorially removed and the adjunct information was updated and added to Section 2, Refer-enced Docu

3、ments, in April 2017.1. Scope1.1 This guide presents a method for predicting values ofreference transition temperature shift (TTS) for irradiatedpressure vessel materials. The method is based on the TTSexhibited by Charpy V-notch data at 41-J (30-ftlbf) obtainedfrom surveillance programs conducted i

4、n several countries forcommercial pressurized (PWR) and boiling (BWR) light-watercooled (LWR) power reactors. An embrittlement correlationhas been developed from a statistical analysis of the largesurveillance database consisting of radiation-induced TTS andrelated information compiled and analyzed

5、by SubcommitteeE10.02. The details of the database and analysis are describedin a separate report (ADJE090015-EA).2,3This embrittlementcorrelation was developed using the variables copper, nickel,phosphorus, manganese, irradiation temperature, neutronfluence, and product form. Data ranges and condit

6、ions for thesevariables are listed in 1.1.1. Section 1.1.2 lists the materialsincluded in the database and the domains of exposure variablesthat may influence TTS but are not used in the embrittlementcorrelation.1.1.1 The range of material and irradiation conditions inthe database for variables used

7、 in the embrittlement correla-tion:1.1.1.1 Copper content up to 0.4 %.1.1.1.2 Nickel content up to 1.7 %.1.1.1.3 Phosphorus content up to 0.03 %.1.1.1.4 Manganese content within the range from 0.55 to 2.0%.1.1.1.5 Irradiation temperature within the range from 255 to300C (491 to 572F).1.1.1.6 Neutron

8、 fluence within the range from11021n/m2to21024n/m2(E 1 MeV).1.1.1.7 A categorical variable describing the product form(that is, weld, plate, forging).1.1.2 The range of material and irradiation conditions inthe database for variables not included in the embrittlementcorrelation:1.1.2.1 A533 Type B C

9、lass 1 and 2, A302 Grade B, A302Grade B (modified), and A508 Class 2 and 3. Also, Europeanand Japanese steel grades that are equivalent to these ASTMGrades.1.1.2.2 Submerged arc welds, shielded arc welds, and elec-troslag welds having compositions consistent with those of thewelds used to join the b

10、ase materials described in 1.1.2.1.1.1.2.3 Neutron fluence rate within the range from31012n/m2/sto51016n/m2/s (E 1 MeV).1.1.2.4 Neutron energy spectra within the range expected atthe reactor vessel region adjacent to the core of commercialPWRs and BWRs (greater than approximately 500MW elec-tric).1.

11、1.2.5 Irradiation exposure times of up to 25 years inboiling water reactors and 31 years in pressurized waterreactors.1.2 It is the responsibility of the user to show that theconditions of interest in their application of this guide areaddressed adequately by the technical information on whichthe gu

12、ide is based. It should be noted that the conditionsquantified by the database are not distributed evenly over therange of materials and irradiation conditions described in 1.1,and that some combination of variables, particularly at the1This guide is under the jurisdiction of ASTM Committee E10 on N

13、uclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved Feb. 1, 2015. Published April 2015. Originallyapproved in 1983. Last previous edition approved in 2007 as E900 02(2007). DOI:10.1520/E

14、0900-15E01.2Available from ASTM International Headquarters. Order Adjunct No.ADJE090015-EA.3To inform the TTS prediction of Section 5 of this guide, the E10.02Subcommittee decided to limit the data considered to Charpy shift values (T41J)measured from irradiations conducted in PWRs and BWRs. A datab

15、ase of 1,878Charpy TTS measurements was compiled from surveillance reports on operating anddecommissioned light water reactors of Western design from 13 countries (Brazil,Belgium, France, Germany, Italy, Japan, Mexico, The Netherlands, South Korea,Sweden, Switzlerland, Taiwan, and the United States)

16、, and from the technicalliterature. For each data record, the following information had to be available:fluence, fluence rate, irradiation temperature, and % content of Cu, Ni, P, and Mn.Reports and technical papers documenting the results of research programsconducted in material test reactors were

17、 also reviewed. Data from these sources wasincluded in the database for information, but was not used in the development of theTTS prediction of Section 5 of this guide.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United StatesThis international

18、 standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.1

19、extremes of the data range are under-represented. Particularattention is warranted when the guide is applied to conditionsnear the extremes of the data range used to develop the TTSequation and when the application involves a region of the dataspace where data is sparse. Although the embrittlement c

20、orre-lation developed for this guide was based on statistical analysisof a large database, prudence is required for applications thatinvolve variable values beyond the ranges specified in 1.1. Dueto strong correlations with other exposure variables within thedatabase (that is, fluence), and due to t

21、he uneven distribution ofdata within the database (for example, the irradiation tempera-ture and flux range of PWR and BWR data show almost nooverlap) neither neutron fluence rate nor irradiation timesufficiently improved the accuracy of the predictions to merittheir use in the embrittlement correla

22、tion in this guide. Futureversions of this guide may incorporate the effect of neutronfluence rate or irradiation time, or both, on TTS, as such effectsare described in (1).4The irradiated material database, thetechnical basis for developing the embrittlement correlation,and issues involved in its a

23、pplication, are discussed in aseparate report (ADJE090015-EA). That report describes thenine different TTS equations considered in the development ofthis guide, some of which were developed using more limiteddatasets (for example, national program data (2, 3). If thematerial variables or exposure co

24、nditions of a particularapplication fall within the range of one of these alternatecorrelations, it may provide more suitable guidance.1.3 This guide is expected to be used in coordination withseveral standards addressing irradiation surveillance of light-water reactor vessel materials. Method of de

25、termining theapplicable fluence for use in this guide are addressed in GuidesE482, E944, and Test Method E1005. The overall applicationof these separate guides and practices is described in PracticeE853.1.4 The values stated in SI units are to be regarded asstandard. The values given in parentheses

26、are mathematicalconversions to U.S. Customary units that are provided forinformation only and are not considered standard.1.5 This standard guide does not define how the TTS shouldbe used to determine the final adjusted reference temperature,which would typically include consideration of the transit

27、iontemperature before irradiation, the predicted TTS, and theuncertainties in the shift estimation method.1.6 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 an

28、d health practices and determine the applica-bility of regulatory limitations prior to use.1.7 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standar

29、ds, Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standards:5A302 Specification for Pressure Vessel Plates, Alloy Steel,Manganese-Molybdenum and Manganese-Molybdenum-NickelA508 Specification for Quenched

30、and Tempered Vacuum-Treated Carbon and Alloy Steel Forgings for PressureVesselsA533 Specification for Pressure Vessel Plates, Alloy Steel,Quenched and Tempered, Manganese-Molybdenum andManganese-Molybdenum-NickelE185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power

31、 Reactor VesselsE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel SurveillanceE693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements PerAtom (DPA)E853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance

32、ResultsE944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor SurveillanceE1005 Test Method for Application and Analysis of Radio-metric Monitors for Reactor Vessel SurveillanceE2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power React

33、or Ves-sels2.2 ASTM Adjunct:2ADJE090015-EA Technical Basis for the Equation Used toPredict Radiation-Induced Transition Temperature Shift inReactor Vessel Materials3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 best-estimate chemical compositionthe best-estimate chemical comp

34、osition (copper Cu, nickel Ni,phosphorus P, and manganese Mn in %) may be establishedusing one of the following methods: (1) Use a simple mean fora small set of uniformly distributed data; that is, sum themeasurements and divide by the number of measurements; (2)Use a weighting process for a non-uni

35、formly distributed dataset, especially when the number of measurements from onesource are much greater in terms of material volume analyzed.For a plate, a unique sample could be a set of test specimenstaken from one corner of the plate. For a weldment, a uniquesample would be a set of test specimens

36、 taken from a uniqueweld deposit made with a specific electrode heat. A simplemean is calculated for test specimens comprising each uniquesample, the sample means are then added, and the sum isdivided by the number of unique samples to get the sampleweighted mean; (3) Use an alternative weighting sc

37、heme whenother factors have a significant influence and a physical model4The boldface numbers in parentheses refer to a list of references at the end ofthis standard.5For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual B

38、ook of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.E900 1512can be established. For the preceding, the best estimate for thesample should be used if evaluating surveillance data from thatsample.3.1.1.1 DiscussionFor cases where no chemical analys

39、ismeasurements are available for a heat of material, the upperlimiting values given in the material specifications to which thevessel was built may be used.Alternately, generic mean valuesfor the class of material may be used.3.1.1.2 DiscussionIn all cases where engineering judg-ment is used to sele

40、ct a best estimate copper, nickel,phosphorus, or manganese content, the rationale shall bedocumented which formed the basis for the selection.3.1.2 fluence ()in this guide the term “fluence” refers tothe fast (E 1MeV) neutron fluence, that is, the number ofneutrons per square centimeter with energy

41、greater than 1.0MeV at the location of interest.3.1.3 fluence rate()in this guide the term “fluence rate”refers to the fast (E 1MeV) neutron fluence rate, that is, thenumber of neutrons per square centimeter per unit time withenergy greater than 1.0 MeV at the location of interest. This isalso refer

42、red to as fast neutron flux.3.1.4 SRMStandard Reference Material. Also known ascorrelation monitor material.3.1.5 Tirradiation temperature at full power, in C, givenby the estimated time-weighted average (based on the meantemperature over each fuel cycle) cold leg temperature forpressurized water re

43、actors (PWRs) and recirculation tempera-ture for boiling water reactors (BWRs).3.1.6 TTSthe mean value of transition temperature shiftpredicted by the embrittlement correlation.4. Significance and Use4.1 Operation of commercial power reactors must conformto pressure-temperature limits during heatup

44、and cooldown toprevent over-pressurization at temperatures that might causenon-ductile behavior in the presence of a flaw. Radiationdamage to the reactor vessel is compensated for by adjustingthe pressure-temperature limits to higher temperatures as theneutron damage accumulates. The present practic

45、e is to basethat adjustment on the TTS produced by neutron irradiation asmeasured at the Charpy V-notch 41-J (30-ftlbf) energy level.To establish pressure temperature operating limits during theoperating life of the plant, a prediction of TTS must be made.4.1.1 In the absence of surveillance data fo

46、r a given reactormaterial (see Practice E185 and E2215), the use of calculativeprocedures are necessary to make the prediction. Even whencredible surveillance data are available, it will usually benecessary to interpolate or extrapolate the data to obtain a TTSfor a specific time in the plant operat

47、ing life.The embrittlementcorrelation presented herein has been developed for thosepurposes.4.2 Research has established that certain elements, notablycopper (Cu), nickel (Ni), phosphorus (P), and manganese (Mn),cause a variation in radiation sensitivity of reactor pressurevessel steels. The importa

48、nce of other elements, such as silicon(Si), and carbon (C), remains a subject of additional research.Copper, nickel, phosphorus, and manganese are the key chem-istry parameters used in developing the calculative proceduresdescribed here.4.3 Only power reactor (PWR and BWR) surveillance datawere used

49、 in the derivation of these procedures. The measureof fast neutron fluence used in the procedure is n/m2(E1MeV). Differences in fluence rate and neutron energy spectraexperienced in power reactors and test reactors have not beenaccounted for in these procedures.5. Calculative Procedure for Transition TemperatureShift (TTS )5.1 The mean value of TTS, in C, is calculated as followsusing the embrittlement correlation developed:4TTS 5 TTS11TTS2(1)where:TTS15 A 59 1.8943 310212 0.5695S1.8 T132550D25.47S0.09 1P0.012D0.216S1.66 1Ni8.540.63D0.39SMn1.3