ASTM E636-2014 2207 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E&8201 706 &40 IH&41 《核动力反应堆容器补充监测试验的标准实施指南 E706 40 IH41》.pdf

《ASTM E636-2014 2207 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E&8201 706 &40 IH&41 《核动力反应堆容器补充监测试验的标准实施指南 E706 40 IH41》.pdf》由会员分享，可在线阅读，更多相关《ASTM E636-2014 2207 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E&8201 706 &40 IH&41 《核动力反应堆容器补充监测试验的标准实施指南 E706 40 IH41》.pdf（7页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: E636 14Standard 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 mechanical properties of thereactor vessel steels.1.2 This guide provides recommen

4、dations 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 also given. Refer-ence is made to other ASTM test meth

5、ods 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.2. Referenced Documents2.1 ASTM Standards:2E23 Test Methods for Notched Bar Impact Testing of Me-tal

6、lic 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 Reconstitution of Irradiated Charpy-SizedSpecimensE1820 Test Method for Meas

7、urement 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 Nuclear Power Reactor Ves-selsE2298 Test Method for Instrumented Impact Testing ofM

8、etallic 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 reactor vessel materials, specificallymechanical property changes that occur

9、 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 Mechanical Property Test4.1 Fracture Toughness TestThis test involves the dy-nami

10、c 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-integral fracturetoughness (JIc), the J-R curve, and the reference temperature(To)

11、 (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 specimenloading or stress intensity increase required for test classifica-tion as quasi-static or dynamic is indicated by the r

12、eferencedtest 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 both, is obtai

13、ned during the test to determine anestimate of material dynamic fracture toughness properties.1This 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.C

14、urrent edition approved Jan. 1, 2014. Published February 2014. Originallyapproved in 1983. Last previous edition approved in 2010 as E636 10. DOI:10.1520/E0636-14.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book

15、 of 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.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. Unite

16、d States1Testing 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 specimens usinga conventional tester (Test Methods E23) equipped withsupplemental instrumentation

17、 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 (upper shelf) fracturebehavior.4.4 Ot

18、her mechanical property tests not covered by ASTMstandards, for example, miniature, nondestructive,nonintrusive, or in-situ testing techniques, can be utilized toaccommodate limitations of material availability or irradiationfacility configuration, or both. However, the user shouldestablish the meth

19、ods 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 surveillance testing be taken from the quarterthickness location of plate and forging materials, as

20、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 recommended that the specimens be taken f

21、roma 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 and forging materials. Specimens havi

22、ng 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 andperpendicular to the weldment surface, with t

23、he 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 deposits, the notch also shouldbe located

24、 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 reference for post-irradiationtesting.

25、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 Specimen MarkingA suitable specimenidentification, marking, and documentation system shall beused w

26、hereby 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 variations through the weldmentthickness.5.1.2 PreparationAll specimens shall be prepared frommat

27、erial 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 other specimen geometries, itmust have bee

28、n 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.5.1.2.3 Fatigue Prec

29、rackingFatigue 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,FIG. 1 Specimen Orientation an

30、d 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 142sections 7.4.5.1 and 7.4.5.2, shall be applied by taking intoaccount, in addition to temperature, also the

31、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 precracking temperature) and YST(yield strength at testtemperature) shall include the effect of ir

32、radiation/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 documentedin the test report. As a precaution, it is recommended to applya value of Kmaxas low as practical

33、ly 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 irradiation exposure condi-tions should be followed. The larger size of some supplementaltest specimens

34、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 specimensmay be irradiated in the same capsule as the specimensrequired by Practice E185 when supp

35、lemental 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 in the test machine are generally required. Fornotched or precracked Charpy-sized impact specimens

36、, 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 necessary. Remote testing equipment shallsatisfy the tolerances and accuracy requirements of the

37、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 E2215 prior to supplemen-tal specimen testing to establish a basis for selecting testtemperatures f

38、or 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 E185. Emphasis should be placed on the reporting oftensile properties with fracture toughness test r

39、esults. 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, etc.) to the testing equipment must be indicated.Pertinent testing procedures used also shall be r

40、eported.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 from other supplemental surveillance mechani-cal property tests, should be included in the report

41、 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 Test6.1 Specimen Design and Possible Modifications:6.1.1 SpecimenThe compact, single-edge bend or

42、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 testing.6.1.2 Possible Design ModificationModified specimensare useful when test stock or irradiatio

43、n 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 modifiedafter irradiation to improve their measuring capabilities. Forexample, many early pressurized wat

44、er 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 occurin the loading arms of these specimens and the tests becomeinvalid. However, techniques have be

45、en 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 specimendesigns may be employed for irradiation provided that it isshown in advance that their use will not

46、 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 The pinhole spacings for compact specimens recom-mended in Test Method E399 and Test Methods E1820

47、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,

48、 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 performed at temperatureswhere the specimen ultimately fractures by cleavage, the cracksize-to-width ratio, a/W, should range between 0.45 and 0

49、.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 that thespecimen thickness, B, and the initial remaining ligament, bo,be greater than the value of 10JQ/Y, where JQis a provisional4The boldface numbers in parentheses refer to a list of references at the end ofthis guide.E636 143value of