ASTM E2215-2010 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels《轻水中型核动力反应堆罐监测室评估的标准实施规程》.pdf

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1、Designation: E2215 10Standard Practice forEvaluation of Surveillance Capsules from Light-WaterModerated Nuclear Power Reactor Vessels1This standard is issued under the fixed designation E2215; the number immediately following the designation indicates the year oforiginal adoption or, in the case of

2、revision, 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.1. Scope1.1 This practice covers the evaluation of test specimensand dosimetry from light water moderated nu

3、clear powerreactor pressure vessel surveillance capsules.1.2 This practice is one of a series of standard practices thatoutline the surveillance program required for nuclear reactorpressure vessels. The surveillance program monitors theradiation-induced changes in the ferritic steels that compriseth

4、e beltline of a light-water moderated nuclear reactor pressurevessel.1.3 This practice along with its companion surveillanceprogram practice, Practice E185, is intended for application inmonitoring the properties of beltline materials in any light-water moderated nuclear reactor.21.4 Modifications t

5、o the standard test program and supple-mental tests are described in Guide E636.1.5 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.2. Referenced Documents2.1 ASTM Standards:3A370 Test Methods and Definitions for Mechanical Tes

6、tingof Steel ProductsE8/E8M Test Methods for Tension Testing of MetallicMaterialsE21 Test Methods for Elevated Temperature Tension Testsof Metallic MaterialsE23 Test Methods for Notched Bar Impact Testing ofMetallic MaterialsE170 Terminology Relating to Radiation Measurements andDosimetryE185 Practi

7、ce for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE208 Test Method for Conducting Drop-Weight Test toDetermine Nil-Ductility Transition Temperature of FerriticSteelsE509 Guide for In-Service Annealing of Light-Water Mod-erated Nuclear Reactor VesselsE560 Pr

8、actice for Extrapolating Reactor Vessel SurveillanceDosimetry Results, E 706(IC)4E636 Guide for Conducting Supplemental SurveillanceTests for Nuclear Power Reactor Vessels, E 706 (IH)E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)E900 Guide for Pre

9、dicting Radiation-Induced TransitionTemperature Shift in Reactor Vessel Materials, E706 (IIF)E1214 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 Fractu

10、re Tough-nessE1921 Test Method for Determination of Reference Tem-perature, To, for Ferritic Steels in the Transition Range2.2 ASME Standards:5American Society of Mechanical Engineers, Boiler andPressure Vessel Code, Sections III and XI5ASME Boiler and Pressure Vessel Code Case N-629, Use ofFracture

11、 Toughness Test Data to Establish ReferenceTemperature for Pressure Retaining Materials, Section XI,Division 1ASME Boiler and Pressure Vessel Code Case N-631 Use ofFracture Toughness Test Data to Establish ReferenceTemperature for Pressure Retaining Materials Other ThanBolting for Class 1 Vessels, S

12、ection III, Division 11This 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 March 1, 2010. Published April 2010. Original

13、lyapproved in 2002. Last previous edition approved in 2002 as E221502. DOI:10.1520/E2215-10.2Prior to the adoption of these standard practices, surveillance capsule testingrequirements were only contained in Practice E185.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontac

14、t ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.4Withdrawn. The last approved version of this historical standard is referencedon www.astm.org.5Available fromAmerican Society of Mechanica

15、l Engineers, Third ParkAvenue,New York, NY 10016.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.3. Terminology3.1 Definitions:3.1.1 base metalas-fabricated plate material or forgingmaterial other than a weld or its corresponding hea

16、t-affected-zone (HAZ).3.1.2 beltlinethe irradiated 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 suficient neutron damage to wa

17、rrant consideration inthe selection of surveillance materials.3.1.3 Charpy transition temperature curvea graphic orcurve-fitted, or both, presentation of absorbed energy, lateralexpansion, or fracture appearance as a function of test tem-perature, extending over a range including the lower shelf (5

18、%or less shear fracture appearance), transition region, and theupper shelf (95 % or greater shear fracture appearance).3.1.4 Charpy transition temperature shiftthe difference inthe 40.7 J (30 ft-lbf) index temperatures for the best fit(average) Charpy absorbed energy curve measured before andafter i

19、rradiation.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 Charpy upper-shelfonset; specimens tested at temperatures greater than 83C(150F) above the Charpy upper-shelf onset shall not bein

20、cluded, unless no data are available between the onsettemperature and onset +83C (+150F).3.1.6 Charpy upper-shelf onsetthe test temperature abovewhich the fracture appearance of all Charpy specimens testedis at or above 95 % shear.3.1.7 end-of-license (EOL)the design lifetime in terms ofyears corres

21、ponding to the operating license period.3.1.8 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.3.1.9 index temperaturethe temperatu

22、re corresponding toa predetermined level of absorbed energy, lateral expansion, orfracture appearance obtained from the best-fit (average)Charpy transition curve.3.1.10 lead factorthe ratio of the peak neutron fluence(E 1 MeV) at the specimens in a surveillance capsule to thepeak neutron fluence (E

23、1 MeV) at the reactor pressure vesselinside surface.3.1.10.1 DiscussionChanges in the reactor operating pa-rameters and fuel management may cause the lead factor tochange.3.1.11 limiting materialsthe weld and base material withthe highest predicted transition temperature at EOL determinedby adding t

24、he appropriate transition temperature shift to theunirradiated RTNDT. The reference temperature shift can bedetermined from the relationship found in Guide E900. Thebasis for selecting the limiting material shall be documented.3.1.12 reference materialany steel that has been charac-terized as to the

25、 sensitivity of its tensile, impact and fracturetoughness properties to neutron radiation embrittlement.3.1.13 reference temperature (RTNDT)see subarticle NB-2300 of the ASME Boiler and Pressure Vessel Code, SectionIII, “Nuclear Power Plant Components” for the definition ofRTNDTfor unirradiated mate

26、rial based on Charpy (Test MethodE23) and drop weight tests (Test Method E208). ASME CodeCases N-629 and N-631 provide an alternative definition forthe reference temperature (RTTo) based on fracture toughnessproperties (Test Method E1921).3.1.14 standby capsulea surveillance capsule meeting therecom

27、mendations of this practice that is in the reactor vesselirradiation location, but whose withdrawal is not required bythis practice.3.2 Neutron Exposure Terminology:3.2.1 Definitions of terms related to neutron dosimetry andexposure are provided in Terminology E170.4. Significance and Use4.1 Neutron

28、 radiation effects are considered in the design oflight-water moderated nuclear power reactors. Changes insystem operating parameters may be made throughout theservice life of the reactor to account for these effects. Asurveillance program is used to measure changes in theproperties of actual vessel

29、 materials due to the irradiationenvironment. This practice describes the criteria that should beconsidered in evaluating surveillance program test capsules.4.2 Prior to the first issue date of this standard, the design ofsurveillance programs and the testing of surveillance capsuleswere both covere

30、d in a single standard, Practice E185. Betweenits provisional adoption in 1961 and its replacement linked tothis standard, Practice E185 was revised many times (1966,1970, 1973, 1979, 1982, 1993 and 1998). Therefore, capsulesfrom surveillance programs that were designed and imple-mented under early

31、versions of the standard were often testedafter substantial changes to the standard had been adopted. Forclarity, the standard practice for surveillance programs hasbeen divided into the new Practice E185 that covers the designof new surveillance programs and this standard practice thatcovers the te

32、sting and evaluation of surveillance capsules.Modifications to the standard test program and supplementaltests are described in Guide E636.4.3 This standard practice is intended to cover testing andevaluation of all light-water moderated reactor pressure vesselsurveillance capsules. The practice is

33、applicable to testing ofcapsules from surveillance programs designed and imple-mented under all previous versions of Practice E185.4.4 The radiation-induced changes in the properties of thevessel are generally monitored by measuring the Charpy indextemperatures, the Charpy upper-shelf energy and the

34、 tensileproperties of specimens from the surveillance program cap-sules. The significance of these radiation-induced changes isdescribed in Practice E185. The application of this data is thesubject of Guide E900 and other documents listed in Section 2.4.5 Alternative methods exist for testing survei

35、llance cap-sule materials. Some supplemental and alternative testingmethods are available as indicated in Guide E636. Directmeasurement of the fracture toughness is also feasible usingthe ToReference Temperature method defined in Test MethodE1921 or J-integral techniques defined in Test Method E1820

36、.Additionally, hardness testing can be used to supplementE2215 102standard methods as a means of monitoring the radiationresponse of the materials.4.6 The methodology to be used in the analysis and inter-pretation of neutron dosimetry data and the determination ofneutron fluence is defined in Practi

37、ce E853.4.7 Guide E900 describes the bases used to evaluate theradiation-induced changes in Charpy transition temperature forreactor vessel materials and provides a methodology forpredicting future values.4.8 Guide E509 provides direction for development of aprocedure for conducting an in-service th

38、ermal anneal of alight-water cooled nuclear reactor vessel and demonstrating theeffectiveness of the procedure including a post-annealingvessel radiation surveillance program.5. Determination of Capsule Condition5.1 Visual ExaminationA complete visual exam of thecapsule condition should be completed

39、 upon receipt and duringdisassembly at the testing laboratory. External identificationmarks on the capsule shall be verified. Signs of damage ordegradation of the capsule exterior shall be recorded.5.2 Capsule ContentThe specimen loading pattern shouldbe compared to the capsule fabrication records a

40、nd anydeviations shall be noted. Any evidence of corrosion or otherdamage to the specimens shall also be noted. The condition ofany thermal monitors shall be noted and recorded.5.3 Irradiation Temperature HistoryThe average capsuletemperature during full power operation shall be estimated foreach re

41、actor fuel cycle prior to capsule removal. The localreactor coolant temperature may be used as a reasonableapproximation. In a typical pressurized water reactor, thecoolant inlet temperature may be used as an estimate of thecapsule irradiation temperature using a time-weighted average(see Guide E900

42、). In a typical boiling water reactor, therecirculation temperature may be used as an estimate of thecapsule irradiation temperature.5.4 Peak TemperatureTemperature monitors shall be ex-amined and any evidence of melting shall be recorded inaccordance with Guide E1214.6. Measurement of Irradiation E

43、xposure6.1 The power history of the reactor for all cycles prior tocapsule removal shall be recorded. Vessel dimensional infor-mation and capsule locations shall be provided for the evalu-ation of irradiation exposure.6.2 The neutron fluence rate, neutron energy spectrum andneutron fluence of the su

44、rveillance specimens and the corre-sponding maximum values for the reactor vessel shall bedetermined in accordance with Practices E853 and E560.6.3 Neutron fluence rate and fluence values (E 1 MeV)and dpa rate and dpa values shall be determined and recordedusing a calculated spectrum adjusted or val

45、idated by dosimetrymeasurements.7. Measurement of Mechanical Properties7.1 Tension Tests:7.1.1 MethodTension testing shall be conducted in accor-dance with Test Methods E8/E8M and E21.7.1.2 Test TemperatureIn general, the test temperaturesfor each material shall include room temperature, servicetemp

46、erature, and, if a specimen is available, one intermediatetemperature to define the strength versus temperature relation-ship. Specific consideration should be given to the specifictemperatures at which unirradiated specimens have beentested.7.1.3 MeasurementsDetermine yield strength, tensilestrengt

47、h, total and uniform elongation and reduction of area.7.2 Charpy Tests:7.2.1 MethodCharpy tests shall be conducted in accor-dance with Test Methods and Definitions A370 and TestMethod E23. Instrumented tests are recommended and shouldbe performed in accordance with Guide E636. Broken Charpyspecimens

48、 may be reconstituted for supplemental testing inaccordance with Guide E1253.7.2.2 Test TemperatureSpecimens for each material shallbe tested at temperatures selected to define the full energytransition curve. Particular emphasis should be placed ondefining the 40.7 J (30 ft-lbf) index temperature a

49、nd theupper-shelf energy level. It is recommended that upper-shelfCharpy tests be conducted using at least three specimens testedand evaluated in accordance with 3.1.5 of this practice.Instrumented tests are recommended and should be performedin accordance with Guide E636.7.2.3 MeasurementsFor each test specimen, measure theimpact energy, lateral expansion, and percent shear fractureappearance.7.3 Hardness Tests (Optional)Hardness tests may be per-formed on irradiated Charpy specimens. The measurementsshall be taken (prior to Charpy testing, if possible,