ASTM E185-2015e1 0076 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels《轻水冷却核反应堆容器的监督程序设计的标准实施规程》.pdf

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1、Designation: E185 151Standard Practice forDesign of Surveillance Programs for Light-Water ModeratedNuclear Power Reactor Vessels1This standard is issued under the fixed designation E185; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revisi

2、on, 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.1NOTEParagraph X1.8 was corrected editorially in October 2015.1. Scope1.1 This practice covers procedures for desi

3、gning a surveil-lance program for monitoring the radiation-induced changes inthe mechanical properties of ferritic materials in light-watermoderated nuclear power reactor vessels. New advanced light-water small modular reactor designs with a nominal designoutput of 300 MWe or less have not been spec

4、ifically consid-ered in this practice. This practice includes the minimumrequirements for the design of a surveillance program, selec-tion of vessel material to be included, and the initial schedulefor evaluation of materials.1.2 This practice was developed for all light-water moder-ated nuclear pow

5、er reactor vessels for which the predictedmaximum fast neutron fluence (E 1 MeV) exceeds 1 1021neutrons/m2(11017n/cm2) at the inside surface of the ferriticsteel reactor vessel.1.3 This practice does not provide specific procedures formonitoring the radiation induced changes in properties beyondthe

6、design life. Practice E2215 addresses changes to thewithdrawal schedule during and beyond the design life.1.4 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.NOTE 1The increased complexity of the requirements for a light-water

7、moderated nuclear power reactor vessel surveillance program hasnecessitated the separation of the requirements into three related stan-dards. Practice E185 describes the minimum requirements for design of asurveillance program. Practice E2215 describes the procedures for testingand evaluation of sur

8、veillance capsules removed from a reactor vessel.Guide E636 provides guidance for conducting additional mechanical tests.Asummary of the many major revisions to Practice E185 since its originalissuance is contained in Appendix X1.NOTE 2This practice applies only to the planning and design ofsurveill

9、ance programs for reactor vessels designed and built after theeffective date of this practice. Previous versions of Practice E185 apply toearlier reactor vessels. See Appendix X1.2. Referenced Documents2.1 ASTM Standards:2A370 Test Methods and Definitions for Mechanical Testingof Steel ProductsA751

10、Test Methods, Practices, and Terminology for Chemi-cal Analysis of Steel ProductsE8/E8M Test Methods for Tension Testing of Metallic Ma-terialsE21 Test Methods for ElevatedTemperatureTensionTests ofMetallic MaterialsE23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE170 Terminolo

11、gy Relating to Radiation Measurements andDosimetryE208 Test Method for Conducting Drop-Weight Test toDetermine Nil-Ductility Transition Temperature of Fer-ritic SteelsE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance, E706 (IID)E636 Guide for Conducting Supplemen

12、tal SurveillanceTests for Nuclear Power Reactor Vessels, E 706 (IH)E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance, E 706 (IIC)E853 Practice forAnalysis and Interpretation of Light-WaterReactor Surveillance ResultsE900 Guide for Predicting Radiation-Induced TransitionTempera

13、ture Shift in Reactor Vessel MaterialsE1214 Guide for Use of Melt Wire Temperature Monitorsfor Reactor Vessel Surveillance, E 706 (IIIE)E1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture ToughnessE1921 Test Method for Determination of Refe

14、renceTemperature, To, for Ferritic Steels in the TransitionRange1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.02 on Behavior and Use of Nuclear Structural Materials.Current edition approved Jun

15、e 1, 2015. Published July 2015. Originally approvedin 1961 as E185 61 T. Last previous edition approved in 2010 as E185 10. DOI:10.1520/E0185-15E01.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandar

16、ds volume information, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1E2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power Reac

17、tor Ves-selsE2298 Test Method for Instrumented Impact Testing ofMetallic MaterialsE2956 Guide for Monitoring the Neutron Exposure of LWRReactor Pressure Vessels2.2 ASME Standards:3Boiler and Pressure Vessel Code, Section III SubsectionNB-2000Boiler and Pressure Vessel Code, Section XI NonmandatoryAp

18、pendix A, Analysis of Flaws, and Nonmandatory Ap-pendix G, Fracture Toughness Criteria for ProtectionAgainst Failure3. Terminology3.1 Definitions:3.1.1 base metalas-fabricated plate material or forgingmaterial other than a weld or its corresponding heat-affected-zone (HAZ).3.1.2 beltlinethe irradiat

19、ed region of the reactor vessel(shell material including weld seams and plates or forgings)that directly surrounds the effective height of the active core.Note that materials in regions adjacent to the beltline maysustain sufficient neutron damage to warrant consideration inthe selection of surveill

20、ance materials.3.1.3 Charpy transition temperature curvea graphic or acurve-fitted presentation, or both, of absorbed energy, lateralexpansion, or fracture appearance as functions of testtemperature, extending over a range including the lower shelf(5 % or less shear fracture appearance), transition

21、region, andthe upper shelf (95 % or greater shear fracture appearance).3.1.4 Charpy transition temperature shiftthe difference inthe 41 J (30 ftlbf) index temperatures for the best fit (average)Charpy absorbed energy curve measured before and afterirradiation. Similar measures of temperature shift c

22、an bedefined based on other indices in 3.1.3, but the current industrypractice is to use 41 J (30 ftlbf) and is consistent with GuideE900.3.1.5 Charpy upper-shelf energy levelthe average energyvalue for all Charpy specimen tests (preferably three or more)whose test temperature is at or above the Cha

23、rpy upper-shelfonset; specimens tested at temperatures greater than 83C(150F) above the Charpy upper-shelf onset shall not beincluded, unless no data are available between the onsettemperature and onset +83C (+150F).3.1.6 Charpy upper-shelf onsetthe temperature at whichthe fracture appearance of all

24、 Charpy specimens tested is at orabove 95 % shear.3.1.7 heat-affected-zone (HAZ)plate material or forgingmaterial extending outward from, but not including, the weldfusion line in which the microstructure of the base metal hasbeen altered by the heat of the welding process.3.1.8 index temperaturethe

25、 temperature corresponding toa predetermined level of absorbed energy, lateral expansion, orfracture appearance obtained from the best-fit (average)Charpy transition curve.3.1.9 lead factorthe ratio of the average neutron fluence(E 1 MeV) of the specimens in a surveillance capsule to thepeak neutron

26、 fluence (E 1 MeV) of the correspondingmaterial at the ferritic steel reactor pressure vessel insidesurface calculated over the same time period.3.1.9.1 DiscussionChanges in the reactor operating pa-rameters or fuel management may cause the lead factor tochange.3.1.10 limiting materialstypically the

27、 weld and base ma-terial with the highest predicted transition temperature usingthe projected fluence at the end of design life of each materialdetermined by adding the appropriate transition temperatureshift to the unirradiated RTNDT. Materials that are projected tomost closely approach a regulator

28、y limit at the end of thedesign life should be considered in selecting the limitingmaterial. The transition temperature shift can be determinedfrom the relationship found in Guide E900 or other sources,including regulations. The basis for selecting the limiting weldand base materials shall be docume

29、nted.3.1.11 maximum design fluence (MDF)the maximum pro-jected fluence at the inside surface of the ferritic pressurevessel at the end of design life (if clad, MDF is defined at theinterface of the cladding to the ferritic steel). Changes duringoperation will affect the projected fluence and are add

30、ressed inPractice E2215.3.1.12 reference materialany steel that has been charac-terized as to the sensitivity of its tensile, impact and fracturetoughness properties to neutron radiation-induced embrittle-ment.3.1.13 reference temperature (RTNDT)see subarticle NB-2300 of the ASME Boiler and Pressure

31、 Vessel Code, SectionIII, “Nuclear Power Plant Components” for the definition ofRTNDTfor unirradiated material based on Charpy (Test MethodA370) and drop weight tests (Test Method E208).ASME CodeSection XI, Appendices A and G provide an alternativedefinition for the reference temperature (RTTo) base

32、d onfracture toughness properties (Test Method E1921)3.1.14 standby capsulea surveillance capsule meeting therecommendations of this practice that is in the reactor vesselirradiation location as defined by Practice E185, but the testingof which is not required by this practice.3.2 Neutron Exposure T

33、erminology:3.2.1 Definitions of terms related to neutron dosimetry andexposure are provided in Terminology E170.4. Significance and Use4.1 Predictions of neutron radiation effects on pressurevessel steels are considered in the design of light-watermoderated nuclear power reactors. Changes in system

34、operat-ing parameters often are made throughout the service life of thereactor vessel to account for radiation effects. Due to the3Available from the American Society of Mechanical Engineers, Third ParkAvenue, New York, NY 10016.E185 1512variability in the behavior of reactor vessel steels, a survei

35、l-lance program is warranted to monitor changes in the proper-ties of actual vessel materials caused by long-term exposure tothe neutron radiation and temperature environment of thereactor vessel. This practice describes the criteria that shouldbe considered in planning and implementing surveillance

36、 testprograms and points out precautions that should be taken toensure that: (1) capsule exposures can be related to beltlineexposures, (2) materials selected for the surveillance programare samples of those materials most likely to limit the operationof the reactor vessel, and (3) the test specimen

37、 types areappropriate for the evaluation of radiation effects on the reactorvessel.4.2 The methodology to be used in estimation of neutronexposure obtained for reactor vessel surveillance programs isdefined in Guides E482 and E853.4.3 The design of a surveillance program for a given reactorvessel mu

38、st consider the existing body of data on similarmaterials in addition to the specific materials used for thatreactor vessel. The amount of such data and the similarity ofexposure conditions and material characteristics will determinetheir applicability for predicting radiation effects.5. Surveillanc

39、e Program Design5.1 This section describes the minimum requirements forthe design of a surveillance program for monitoring theradiation-induced changes in the mechanical properties of theferritic materials that compose the reactor vessel.5.2 Surveillance Materials:5.2.1 Materials SelectionThe survei

40、llance materials shallinclude, at minimum, the limiting base metal and the limitingweld. If a limiting material is outside the beltline, the limitingbeltline base and weld materials shall also be included. If thereis no beltline weld, capsules whose target fluence (Table 1)isgreater than two times t

41、he design fluence of the limiting weldare not required to contain weld metal, except that the firstcapsule must contain the limiting weld material.NOTE 3The predicted limiting material may change during operationdue to changes that may occur in the transition temperature shiftprediction formulation,

42、 or other factors. Therefore, it is prudent to includeadditional potentially limiting materials in the surveillance program ascapsule space permits.5.2.2 Material SamplingA minimum surveillance pro-gram shall consist of the material selected in 5.2.1, taken fromthe following: (1) base metal from the

43、 actual plate(s) orforging(s) used in the reactor vessel, and (2) weld metal(s)made with the same heat of weld wire and lot of flux and by thesame welding procedure as that used for the reactor vesselwelds. If a reactor vessel weld is contained in the beltline, it isrecommended that at least one of

44、the base metals used tofabricate the weldment(s) shall be a base metal beltlinematerial included in the surveillance program. Surveillance testspecimens shall be removed from full reactor vessel thicknesssamples.5.2.2.1 Any non-actual reactor vessel base metal used tofabricate the surveillance weld

45、shall have a similar nominalchemical composition and thickness to the reactor vessel basemetal. Any archived non-actual reactor vessel base metal(s)used to fabricate the surveillance weldment(s) shall be clearlymarked with “Not actual reactor vessel base metal - Do not usefor base metal or HAZ speci

46、men” or similar, and shall beclearly identified in the associated documentation as non-actualreactor vessel base metal.NOTE 4Experience has shown that it is no longer necessary to includethe HAZ material in the surveillance program. However, it is recom-mended that the HAZ material be included with

47、the archive material (see5.2.5).45.2.3 Fabrication HistoryThe fabrication history(austenitizing, quench and tempering, and post-weld heattreatment) of the surveillance materials shall be fully represen-tative of the fabrication history of the reactor vessel materialsselected in 5.2.1 and shall be re

48、corded.5.2.4 Chemical Analysis RequirementsThe chemicalanalysis required by the appropriate product specifications forthe surveillance materials (base metal and as-deposited weldmetal) shall be recorded and shall include copper (Cu), nickel(Ni), manganese (Mn), phosphorus (P), sulfur (S), silicon (S

49、i),carbon (C), and vanadium (V), as well as all other alloying andresidual elements commonly analyzed for in low-alloy steelproducts. The product analysis shall be as described in TestMethod A751 and verified by analyzing samples selected fromthe base metal and the as-deposited weld metal used for thesurveillance program.5.2.5 Archive MaterialsEnough material to fill a mini-mum of three additional capsules per 5.4.2 beyond the mini-mum number required for the program as defined in 5.8.1 shallbe retained with full documentation and identificatio