ASTM E636-2014e1 3831 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels《核动力反应堆容器补充监测试验的标准实施指南》.pdf

《ASTM E636-2014e1 3831 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels《核动力反应堆容器补充监测试验的标准实施指南》.pdf》由会员分享，可在线阅读，更多相关《ASTM E636-2014e1 3831 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels《核动力反应堆容器补充监测试验的标准实施指南》.pdf（7页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: E636 141Standard Guide forConducting Supplemental Surveillance Tests for NuclearPower Reactor Vessels1This 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, the year o

2、f last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1NOTEThe title of this guide was updated editorially in May 2017.1. Scope1.1 This guide discusses test procedures that can be us

3、ed inconjunction with, but not as alternatives to, those 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 mechanical properties of the

4、reactor 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 post-irradiation test planning. Guidance on datareduction and computational procedures is

5、also given. Refer-ence is made to other ASTM test methods for the physicalconduct of specimen tests and for raw data acquisition.1.3 The values stated in SI units are to be regarded as thestandard. The values given in parentheses are for informationonly.1.4 This international standard was developed

6、in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents

7、2.1 ASTM Standards:2E23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE399 Test Method for Linear-Elastic Plane-Strain FractureToughness KIcof Metallic MaterialsE1253 Guide for

8、 Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Measurement of Fracture ToughnessE1921 Test Method for Determination of ReferenceTemperature, To, for Ferritic Steels in the TransitionRangeE2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclea

9、r Power Reactor Ves-selsE2298 Test Method for Instrumented Impact Testing ofMetallic Materials2.2 ASME Standards:3ASME Boiler and Pressure Vessel Code, Section III Subsec-tion NB (Class 1 Components)3. Significance and Use3.1 Practices E185 and E2215 describe a minimum programfor the surveillance of

10、 reactor vessel materials, specificallymechanical property changes that occur in service. This guidemay be applied in order to generate additional information onradiation-induced property changes to better assist the deter-mination of the optimum reactor vessel operation schemes.4. Supplemental Mech

11、anical Property Test4.1 Fracture Toughness TestThis test involves the dy-namic or static testing of a fatigue-precracked specimen duringwhich a record of force versus displacement is used todetermine material fracture toughness properties such as theplane strain fracture toughness (KIc), the J-integ

12、ral fracturetoughness (JIc), the J-R curve, and the reference temperature(To) (see Test Methods E399, E1820, and E1921, respectively).These test methods generally apply to elastic, ductile-to-brittletransition, or fully plastic behavior. The rate of specimen1This guide is under the jurisdiction of A

13、STM 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 Jan. 1, 2014. Published February 2014. Originallyapproved in 1983. Last previous edition approved in 2010 as E63

14、6 10. DOI:10.1520/E0636-14E01.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Available from American Societ

15、y of Mechanical Engineers, 345 E. 47th St.,New York, NY 10017.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United StatesThis international standard was developed in accordance with internationally recognized principles on standardization establi

16、shed 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.1loading or stress intensity increase required for test classifica-tion as quasi-static or dynamic is indica

17、ted by the referencedtest methods. All three test methods specify a lower limit onloading rate for dynamic tests.4.2 Fracture Toughness Test at Impact Loading RatesThistest involves impact testing of Charpy-type specimens thathave been fatigue precracked.Aforce versus deflection or timerecord, or bo

18、th, is obtained during the test to determine anestimate of material dynamic fracture toughness properties.Testing and data analysis shall be performed in accordancewith Annex A17 of Test Method E1820.4.3 Instrumented Charpy V-Notch TestThis test involvesthe impact testing of standard Charpy V-notch

19、specimens usinga conventional tester (Test Methods E23) equipped withsupplemental 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 initiati

20、on and propaga-tion energies, and to identify fully ductile (upper shelf) fracturebehavior.4.4 Other mechanical property tests not covered by ASTMstandards, for example, miniature, nondestructive,nonintrusive, or in-situ testing techniques, can be utilized toaccommodate limitations of material avail

21、ability or irradiationfacility configuration, or both. However, the user shouldestablish the methods technical validity and correlation withexisting test methods.5. General Test Requirements5.1 Specimen Orientation and Preparation:5.1.1 OrientationIt is recommended that specimens forsupplemental sur

22、veillance testing be taken from the quarterthickness location 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 fo

23、r special studies, if required. For welddeposits, it is recommended 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

24、 transverse orientation (T-L, per Test MethodE399) in plate 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 pla

25、ne of fracture parallel to the welding direction andperpendicular 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 nor

26、mal to the plate, forging,or weldment surface. For weld deposits, 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 l

27、ocation of the weld fusionlines be permanently marked for reference for post-irradiationtesting. The general appearance of the etched weld deposit interms of individual weld bead size (large versus small) and thenumber of weld beads across the weld deposit should bedetermined and recorded.5.1.1.2 Sp

28、ecimen MarkingA suitable specimenidentification, marking, and documentation system shall beused whereby the location and orientation of each specimenwithin the source plate, forging, or weldment can be traced.The traceability of weld specimens is particularly importantbecause of the possibility for

29、variations through the weldmentthickness.5.1.2 PreparationAll 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

30、E1253 shall be followedfor Charpy-sized specimens. For other specimen geometries, itFIG. 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 OrientationE

31、636 1412must 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 control anduniformity

32、.5.1.2.3 Fatigue PrecrackingFatigue precracking of frac-ture toughness specimens shall be performed in the final testingcondition, including material irradiation and annealing, asrequired in Test Method E1820. If this is technically notpractical, the procedure outlined in Test Method E1820,sections

33、7.4.5.1 and 7.4.5.2, shall be applied by taking intoaccount, in addition to temperature, also the effect of irradia-tion and annealing on material yield strength. If irradiation/annealing operations have been applied between specimenprecracking and final testing, the parameters YSf(yield strengthat

34、precracking temperature) and YST(yield strength at testtemperature) shall include the effect of irradiation/annealing inaddition to the effect of temperature. The material yieldstrength in the precracking condition and in the test condition,as well as their temperature dependence, shall be documente

35、din the test report. As a precaution, it is recommended to applya value of Kmaxas low as practically feasible during precrack-ing.5.2 Specimen Irradiation:5.2.1 GeneralThe recommendations of Practice E185concerning the encapsulation of specimens, temperature andneutron fluence monitoring, and irradi

36、ation exposure condi-tions should be followed. The larger size of some supplementaltest specimens may require additional consideration of tem-perature gradients and neutron fluence rate gradients withinindividual specimens and within the specimen capsules.5.2.2 Specimen IrradiationSupplemental test

37、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 controlled area or in a hotcell facility, remote devices for accurately positioning thespecimen

38、in the test machine are generally required. Fornotched or precracked Charpy-sized impact specimens, auto-matic devices to position the specimen on the test anvils arestrongly recommended. Additional remote devices for speci-men heating and cooling and for the attachment of measuringfixtures are also

39、 necessary. Remote testing equipment shallsatisfy the tolerances and accuracy requirements of the appli-cable ASTM standards for the test method(s) employed.5.4 Specimen TestingIt is recommended that post-irradiation Charpy V-notch impact and tensile tests be per-formed in accordance with Practice E

40、2215 prior to supplemen-tal specimen testing to establish a basis for selecting testtemperatures for the supplemental specimens tested under thismethod.5.5 Documentation:5.5.1 The report shall include the reporting requirements onmaterial identification and irradiation history required byPractice E1

41、85. 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 monitoringequipment, and the accuracy to which they operate, will bereported. Any special modifications (for example, force damp-ing equipment,

42、etc.) to the testing equipment must be indicated.Pertinent testing procedures used also shall be reported.5.5.3 To aid in the interpretation of these supplementalsurveillance results, data developed in accordance with Prac-tice E2215, including data from reference correlation monitormaterial or data

43、 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 reconstitution technique shall be given inaccordance with Guide E1253.6. Fracture Toughness

44、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 for design modification (see 6.1.2) for surveillancecapsules, will be used for te

45、sting.6.1.2 Possible Design ModificationModified specimensare useful when test stock or irradiation space is limited, orwhen gamma heating or neutron fluence rate gradients must beminimized. An example of reconstituted Charpy-sized speci-men is illustrated in Fig. 2. Specimens have also been modifie

46、dafter irradiation to improve their measuring capabilities. Forexample, many early pressurized water reactors (PWR) containwedge-opening loaded (WOL) fracture mechanics specimens.These specimens were originally intended for testing in thebrittle fracture regime. For ductile materials, bending can oc

47、curin the loading arms of these specimens and the tests becomeinvalid. However, techniques have been developed to makethese specimens useful for testing under ductile conditions.These include extension of the fatigue precrack or modificationof the specimen dimensions, or both (1).4Modified specimend

48、esigns may be employed for irradiation provided that it isshown in advance that their use will not significantly diminishthe accuracy of the test or alter test results; if correlations withstandard specimen test results have to be employed, theirjustification and accuracy shall be provided.6.1.2.1 T

49、he pinhole spacings for compact specimens recom-mended in Test Method E399 and Test Methods E1820 orE1921 are different. However, this difference does not signifi-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 6.1.3.3.6.1.3.1 Elastic and Elastic-Plastic Fracture BehaviorWhen testing is expected to be performe