ASTM E636-2010 7500 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对核动力反应堆容器进行补充监控试验的标准指南E 706( IH)》.pdf

《ASTM E636-2010 7500 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对核动力反应堆容器进行补充监控试验的标准指南E 706( IH)》.pdf》由会员分享，可在线阅读，更多相关《ASTM E636-2010 7500 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对核动力反应堆容器进行补充监控试验的标准指南E 706( IH)》.pdf（8页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: E636 10Standard Guide forConducting Supplemental Surveillance Tests for NuclearPower Reactor Vessels, E 706 (IH)1This standard is issued under the fixed designation E636; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision,

2、 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 guide discusses test procedures that can be used inconjunction with, but not as alternatives to, tho

3、se required byPractices E185 and E2215 for the surveillance of nuclearreactor vessels. The supplemental mechanical property testsoutlined permit the acquisition of additional information onradiation-induced changes in fracture toughness, notch ductil-ity, and yield strength properties of the reactor

4、 vessel steels.1.2 This guide provides recommendations for the prepara-tion of test specimens for irradiation, and identifies specialprecautions and requirements for reactor surveillance opera-tions and postirradiation test planning. Guidance on datareduction and computational procedures is also giv

5、en. Refer-ence is made to other ASTM test methods for the physicalconduct of specimen tests and for raw data acquisition.2. Referenced Documents2.1 ASTM Standards:2E23 Test Methods for Notched Bar Impact Testing ofMetallic MaterialsE185 Practice for Design of Surveillance Programs forLight-Water Mod

6、erated Nuclear Power Reactor VesselsE399 Test Method for Linear-Elastic Plane-Strain FractureToughness KIcof Metallic MaterialsE1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture Tough-nessE1921 Test Method for Determination of Reference Te

7、m-perature, To, for Ferritic Steels in the Transition RangeE2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power Reactor Ves-selsE2298 Test Method for Instrumented Impact Testing ofMetallic Materials2.2 ASME Standards:3ASME Boiler and Pressure Vessel Code, Se

8、ction III Sub-section NB (Class 1 Components)3. Significance and Use3.1 Practices E185 and E2215 describe a minimum programfor the surveillance of reactor vessel materials, specificallymechanical property changes that occur in service. This guidemay be applied in order to generate additional specifi

9、c fracturetoughness property information on radiation-induced propertychanges to better assist the determination of the optimumreactor vessel operation schemes.4. Supplemental Mechanical Property Test4.1 Fracture Toughness TestThis test involves the dy-namic or static testing of a fatigue-precracked

10、 specimen duringwhich a record of force versus displacement is used todetermine material fracture toughness properties such as theplane strain fracture toughness (KIc), the J-integral fracturetoughness (JIc), the J-R curve, and the reference temperature(T0) (see Test Methods E399, E1820, and E1921,

11、respectively).These test methods generally apply to elastic, ductile-to-brittletransition, or fully plastic behavior. The rate of specimenloading or stress intensity increase required for test classifica-tion as quasi-static or dynamic is indicated by the referencedtest methods. All three test metho

12、ds specify a lower limit onloading rate for dynamic tests.4.2 Fracture Toughness Test at Impact Loading RatesThistest involves impact testing of Charpy V-notch specimens thathave been fatigue precracked.Aforce versus deflection or timerecord, or both, is obtained during the test to determine anestim

13、ate of material dynamic fracture toughness properties.Currently, no standard test method is available for performingand analyzing this test; details on the recommended proceduresare given in 7.17.4 and Appendix Appendix X1.4.3 Instrumented Charpy V-Notch TestThis test involvesthe impact testing of s

14、tandard Charpy V-notch specimens usinga conventional tester (Test Methods E23) equipped with1This guide 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.Cur

15、rent edition approved March 1, 2010. Published April 2010. Originallyapproved in 1983. Last previous edition approved in 2009 as E636 09. DOI:10.1520/E0636-10.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of

16、ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Available from American Society of Mechanical Engineers, 345 E. 47th St.,New York, NY 10017.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United S

17、tates.supplemental instrumentation that provides a force versusdeflection or time record, or both, to augment standard test data(see Test Method E2298). The test record is used primarily toestimate dynamic yield stress, fracture initiation and propaga-tion energies, and to identify fully ductile (up

18、per shelf) fracturebehavior.4.4 Other mechanical property tests not covered by ASTMstandards, for example, miniature, nondestructive, nonintru-sive, or in-situ testing techniques, can be utilized to accommo-date limitations of material availability or irradiation facilityconfiguration, or both. Howe

19、ver, the user should establish themethods technical validity and correlation with existing testmethods.5. General Test Requirements5.1 Specimen Orientation and Preparation:5.1.1 OrientationIt is recommended that specimens forsupplemental surveillance testing be taken from the quarterthickness locati

20、on of plate and forging materials, as defined inNB 2300 of ASME Boiler and Pressure Vessel Code, SectionIII, and at a distance at least one material thickness from aquenched edge. Specimens from near surface material alsomay be considered for special studies, if required. For welddeposits, it is rec

21、ommended that the specimens be taken froma thickness location at least 12.7 mm (12 in.) removed from theroot and the surfaces of the weld. Consistent with PracticeE185, it is further recommended that the specimens be orientedto represent the transverse orientation (T-L, per Test MethodE399) in plate

22、 and forging materials. Specimens having thelongitudinal orientation (L-T, per Test Method E399) also maybe used given sufficient material and space in the surveillancecapsule. For weld deposits, the specimen shall be oriented tomake the plane of fracture parallel to the welding direction andperpend

23、icular to the weldment surface, with the direction ofcrack growth along the welding direction. Examples of speci-men orientations are given in Fig. 1.5.1.1.1 Specimen Notch OrientationThe specimen notchroot in all cases shall be oriented normal to the plate, forging,or weldment surface. For weld dep

24、osits, the notch also shouldbe located at the approximate weld deposit centerline. Thecenterline and the width of the weld deposit about the notchshall be determined from the weld fusion lines revealed byetching. It is recommended that the location of the weld fusionlines be permanently marked for r

25、eference for post-irradiationtesting. The general appearance of the etched weld deposit interms of individual weld bead size (large vs. small) and thenumber of weld beads across the weld deposit should bedetermined and recorded.5.1.1.2 Specimen MarkingA suitable specimen identifica-tion, marking, an

26、d documentation system shall be usedwhereby the location and orientation of each specimen withinthe source plate, forging, or weldment can be traced. Thetraceability of weld specimens is particularly important be-cause of the possibility for variations through the weldmentthickness.5.1.2 Preparation

27、All specimens shall be prepared frommaterial that has been fully heat-treated, including stress-reliefannealing, as recommended in Practice E185.5.1.2.1 ReconstitutionIf reconstituted specimens are to beused, the procedures outlined in Guide E1253 shall be followedfor Charpy-sized specimens. For oth

28、er specimen geometries, itmust have been previously proven that the reconstitutionprocedure has no significant influence on the test result.5.1.2.2 MachiningSpecimens for irradiation should befinish machined on all sides to aid encapsulation in reactorexperiments and to aid radiation temperature con

29、trol anduniformity.5.1.2.3 Fatigue PrecrackingIt is recommended that fa-tigue precracking of specimens be accomplished prior toirradiation to avoid difficulties of precracking following irra-diation. However, fatigue precracking of a specimen followingirradiation is acceptable if a suitable means of

30、 following crackextension in the specimen is established.5.1.2.4 Fatigue Precracking of Postirradiation Heat-Treated SpecimensSome postirradiation heat treatments attemperatures higher than the prior irradiation exposure cancause mechanical property recovery, including reductions inyield strength an

31、d tensile strength and an improvement inFIG. 1 Specimen Orientation and Location in Plate, Forging, andWeld Deposit Materials: A) Crack Plane Orientation Code; B)Plate and Forging Specimen Location and Orientation; C) WeldSpecimen Location and OrientationE636 102fracture toughness toward preirradiat

32、ion levels. Compliancewith Test Methods E399, E1820, and E1921 requires thatfatigue precracking be accomplished in the final heat treatmentcondition. This may be impractical for irradiated specimens.Fatigue precracking before postirradiation heat treatment isacceptable for low temperature heat treat

33、ment typical of reactorvessel annealing. It is believed that fatigue precracking offerritic material specimens prior to heat treatment below 482C(900F) does not alter the test results for the bulk materialproperties as intended.5.2 Specimen Irradiation:5.2.1 GeneralThe recommendations of Practice E1

34、85concerning the encapsulation of specimens, temperature andneutron fluence monitoring, and irradiation exposure condi-tions should be followed. The larger size of some supplementaltest specimens may require additional consideration of tem-perature gradients and neutron flux gradients within individ

35、ualspecimens and within the specimen capsules.5.2.2 Specimen IrradiationSupplemental test specimensmay be irradiated in the same capsule as the specimensrequired by Practice E185 when supplemental results aredesired.5.3 Specimen Handling and Remote Test Equipment:5.3.1 GeneralFor testing in a contro

36、lled area or in a hotcell facility, remote devices for accurately positioning thespecimen in the test machine are generally required. Fornotched or precracked Charpy impact specimens, automaticdevices to position the specimen on the test anvils are stronglyrecommended.Additional remote devices for s

37、pecimen heatingand cooling and for the attachment of measuring fixtures arealso necessary. Remote testing equipment shall satisfy thetolerances and accuracy requirements of the applicable ASTMstandards for the test method(s) employed.5.4 Specimen TestingIt is recommended that postirradia-tion Charpy

38、 V-notch impact and tensile tests be performed inaccordance with Practice E2215 prior to supplemental speci-men testing to establish a basis for selecting test temperaturesfor the supplemental specimens tested under this method.5.5 Documentation:5.5.1 The report shall include the reporting requireme

39、nts onmaterial identification and irradiation history required byPractice E185. Emphasis should be placed on the reporting oftensile properties with fracture toughness test results. See6.1.3.2).5.5.2 Names and models of testing and monitoring equip-ment, and the accuracy to which they operate, will

40、be reported.Any special modifications (for example, force damping equip-ment, etc.) to the testing equipment must be indicated. Perti-nent testing procedures used also shall be reported.5.5.3 To aid in the interpretation of these supplementalsurveillance results, data developed in accordance with Pr

41、ac-tice E2215, including data from reference correlation monitormaterial or data from other supplemental surveillance mechani-cal property tests, should be included in the report or should bereferenced suitably.5.5.4 If reconstituted specimens have been used, informa-tion concerning the reconstituti

42、on technique shall be given inaccordance with Guide E1253.6. Fracture Toughness Test6.1 Specimen Design and Possible Modifications:6.1.1 SpecimenThe compact, single-edge bend or disk-shaped compact specimen of dimensions outlined in TestMethod E399, Test Method E1820, or Test Method E1921,allowing f

43、or design modification (see 6.1.2) for surveillancecapsules, will be used for testing.6.1.2 Possible Design ModificationModified specimensare useful when test stock or irradiation space is limited, orwhen gamma heating or neutron flux gradients must beminimized.An example of reconstituted Charpy-typ

44、e specimenis illustrated in Fig. 2. Specimens have also been modified afterFIG. 2 Example of Reconstituted Charpy-type SpecimenE636 103irradiation to improve their measuring capabilities. For ex-ample, many early pressurized water reactors (PWR) containwedge-opening loaded (WOL) fracture mechanics s

45、pecimens.These specimens were originally intended for testing in thebrittle fracture regimen. For ductile materials, bending canoccur in the loading arms of these specimens and the testsbecome invalid. However, techniques have been developed tomake these specimens useful for testing under ductile co

46、ndi-tions. These include extension of the fatigue precrack ormodification of the specimen dimensions, or both (1).4Modi-fied specimen designs may be employed for irradiation pro-vided that it is shown in advance that their use will notsignificantly diminish the accuracy of the test or alter testresu

47、lts; if correlations with standard specimen test results haveto be employed, their justification and accuracy have to beprovided.6.1.2.1 The pinhole spacings for compact specimens recom-mended in Test Method E399 and Test Methods E1820 orE1921 are different. However, this difference does not signifi

48、-cantly affect the stress field at the crack tip and, therefore,either pinhole spacing is acceptable for surveillance testing (2).6.1.3 Fatigue PrecrackingFatigue precracking shall beperformed in accordance with either Test Method E399, TestMethod E1820, or Test Method E1921 as discussed in 6.1.3.1-

49、6.1.3.3.6.1.3.1 Elastic and Elastic-Plastic Fracture BehaviorWhen testing is expected to be performed at temperatureswhere the specimen ultimately fractures by cleavage, the cracksize-to-width ratio, a/W, should range between 0.45 and 0.55,and precracking should be accomplished in accordance withTest Method E399 or Test Method E1921.6.1.3.2 Fully Plastic BehaviorWhen testing is expected tobe performed in the region characteristic of fully plasticfracture behavior, compliance with Test Method E1820 re-quires the a/W ratio to be between 0.45 and 0.70 and tha