1、Designation: E 636 09Standard Guide forConducting Supplemental Surveillance Tests for NuclearPower Reactor Vessels, E 706 (IH)1This standard is issued under the fixed designation E 636; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revisio
2、n, 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, t
3、hose required byPractices E 185 and E 2215 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 rea
4、ctor 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
5、 given. Refer-ence is made to other ASTM and ISO test methods for thephysical conduct of specimen tests and for raw data acquisi-tion.2. Referenced Documents2.1 ASTM Standards:2E23 Test Methods for Notched Bar Impact Testing ofMetallic MaterialsE 185 Practice for Design of Surveillance Programs forL
6、ight-Water Moderated Nuclear Power Reactor VesselsE 399 Test Method for Linear-Elastic Plane-Strain FractureToughness KIcof Metallic MaterialsE 1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimensE 1820 Test Method for Measurement of Fracture Tough-nessE 1921 Test Method for Determinati
7、on of Reference Tem-perature, To, for Ferritic Steels in the Transition RangeE 2215 Practice for Evaluation of Surveillance Capsulesfrom Light-Water Moderated Nuclear Power Reactor Ves-sels2.2 Other Standards:ASME Boiler and Pressure Vessel Code, Section III Sub-section NB (Class 1 Components)3ISO 1
8、4556 Steel Charpy V-notch Pendulum Impact Test-Instrumented Test Method43. Significance and Use3.1 Practices E 185 and E 2215 describe a minimum pro-gram for the surveillance of reactor vessel materials, specifi-cally mechanical property changes that occur in service. Thisguide may be applied in ord
9、er to generate additional specificfracture toughness property information on radiation-inducedproperty changes to better assist the determination of theoptimum reactor vessel operation schemes.4. Supplemental Mechanical Property Test4.1 Fracture Toughness TestThis test involves the dy-namic or stati
10、c 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(T0) (see Test
11、 Methods E 399, E 1820, and E 1921, respec-tively). These test methods generally apply to elastic, ductile-to-brittle transition, or fully plastic behavior. The rate ofspecimen loading or stress intensity increase required for testclassification as quasi-static or dynamic is indicated by thereferenc
12、ed test methods. All three test methods specify a lowerlimit on loading 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. A force versus deflection or timerecord, or both, is obtain
13、ed during the test to determine anestimate 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 7.1 7.4 and Appendix Appendix X1.4.3 Instrumented Charpy V-Notch TestT
14、his test involvesthe impact testing of standard Charpy V-notch specimens using1This 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.Current edition a
15、pproved Feb. 1, 2009. Published March 2009. Originallyapproved in 1983. Last previous edition approved in 2002 as E 636 02.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, re
16、fer to the standards Document Summary page onthe ASTM website.3Available from American Society of Mechanical Engineers, 345 E. 47th St.,New York, NY 10017.4Available from International Organization for Standardization (ISO), 1 rue deVarembe, Case postale 56, CH-1211, Geneva 20, Switzerland.1Copyrigh
17、t ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.a conventional tester (Test Methods E23) equipped withsupplemental instrumentation that provides a force versusdeflection or time record, or both, to augment standard test data(ISO 14556). The t
18、est record is used primarily to estimatedynamic yield stress, fracture initiation and propagation ener-gies, and to identify fully ductile (upper shelf) fracture behav-ior.4.4 Other mechanical property tests not covered by ASTMstandards, for example, miniature, nondestructive, nonintru-sive, or in-s
19、itu testing techniques, can be utilized to accommo-date limitations of material availability or irradiation facilityconfiguration, or both. However, the user should establish themethods technical validity and correlation with existing testmethods.5. General Test Requirements5.1 Specimen Orientation
20、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 defined inNB 2300 of ASME Boiler and Pressure Vessel Code, SectionIII, and at a distance at least one material thickne
21、ss 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 froma thickness location at least 12.7 mm (12 in.) removed from theroot and the surfaces of the weld. Consistent with P
22、racticeE 185, it is further recommended that the specimens beoriented to represent the transverse orientation (T-L, per TestMethod E 399) in plate and forging materials. Specimenshaving the longitudinal orientation (L-T, per Test MethodE 399) also may be used given sufficient material and space inth
23、e surveillance capsule. For weld deposits, the specimen shallbe oriented to make the plane of fracture parallel to the weldingdirection and perpendicular to the weldment surface, with thedirection of crack growth along the welding direction. Ex-amples of specimen orientations are given in Fig. 1.5.1
24、.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 at the approximate weld deposit centerline. Thecenterline and the width of the weld deposit about the notchshall b
25、e 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. The general appearance of the etched weld deposit interms of individual weld bead size (large vs. small) and thenum
26、ber of weld beads across the weld deposit should bedetermined and recorded.5.1.1.2 Specimen MarkingA suitable specimen identifica-tion, marking, and documentation system shall be usedwhereby the location and orientation of each specimen withinthe source plate, forging, or weldment can be traced. The
27、traceability of weld specimens is particularly important be-cause of the possibility for 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 E 185.5.1.2.1
28、 ReconstitutionIf reconstituted specimens are to beused, the procedures outlined in Guide E 1253 shall befollowed for Charpy-sized specimens. For other specimengeometries, it must have been previously proven that thereconstitution procedure has no significant influence on the testresult.5.1.2.2 Mach
29、iningSpecimens 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 PrecrackingIt is recommended that fa-tigue precracking of specimens be accomplished prior toirradiation to avoid diff
30、iculties of precracking following irra-diation. However, fatigue precracking of a specimen followingirradiation is acceptable if a suitable means of following crackextension in the specimen is established.5.1.2.4 Fatigue Precracking of Postirradiation Heat-Treated SpecimensSome postirradiation heat
31、treatments attemperatures higher than the prior irradiation exposure cancause mechanical property recovery, including reductions inFIG. 1 Specimen Orientation and Location in Plate, Forging, andWeld Deposit Materials: A) Crack Plane Orientation Code; B)Plate and Forging Specimen Location and Orienta
32、tion; C) WeldSpecimen Location and OrientationE636092yield strength and tensile strength and an improvement infracture toughness toward preirradiation levels. Compliancewith Test Methods E 399, E 1820, and E 1921 requires thatfatigue precracking be accomplished in the final heat treatmentcondition.
33、This may be impractical for irradiated specimens.Fatigue precracking before postirradiation heat treatment isacceptable for low temperature heat treatment typical of reactorvessel annealing. It is believed that fatigue precracking offerritic material specimens prior to heat treatment below 482C(900F
34、) does not alter the test results for the bulk materialproperties as intended.5.2 Specimen Irradiation:5.2.1 GeneralThe recommendations of Practice E 185concerning the encapsulation of specimens, temperature andneutron fluence monitoring, and irradiation exposure condi-tions should be followed. The
35、larger size of some supplementaltest specimens may require additional consideration of tem-perature gradients and neutron flux gradients within individualspecimens and within the specimen capsules.5.2.2 Specimen IrradiationSupplemental test specimensmay be irradiated in the same capsule as the speci
36、mensrequired by Practice E 185 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 in the test machine are generally required. Fornotched or
37、precracked Charpy impact specimens, automaticdevices to position the specimen on the test anvils are stronglyrecommended.Additional remote devices for specimen heatingand cooling and for the attachment of measuring fixtures arealso necessary. Remote testing equipment shall satisfy thetolerances and
38、accuracy requirements of the applicable ASTMstandards for the test method(s) employed.5.4 Specimen TestingIt is recommended that postirradia-tion Charpy V-notch impact and tensile tests be performed inaccordance with Practice E 2215 prior to supplemental speci-men testing to establish a basis for se
39、lecting test temperaturesfor the supplemental specimens tested under this method.5.5 Documentation:5.5.1 The report shall include the reporting requirements onmaterial identification and irradiation history required byPractice E 185. Emphasis should be placed on the reporting oftensile properties wi
40、th 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 be reported.Any special modifications (for example, force damping equip-ment, etc.) to the testing equipment must be indicated. Perti-nent testin
41、g 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 E 2215, including data from reference correlation monitormaterial or data from other supplemental surveillance mechani-cal property tests
42、, 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 E 1253.6. Fracture Toughness Test6.1 Specimen Design and Possible Modifications:6.1.1 Specim
43、enThe compact, single-edge bend or disk-shaped compact specimen of dimensions outlined in TestMethod E 399, Test Method E 1820, or Test Method E 1921,allowing for design modification (see 6.1.2) for surveillancecapsules, will be used for testing.6.1.2 Possible Design ModificationModified specimensar
44、e useful when test stock or irradiation space is limited, orwhen gamma heating or neutron flux gradients must beminimized.An example of reconstituted Charpy-type specimenis illustrated in Fig. 2. Specimens have also been modified afterFIG. 2 Example of Reconstituted Charpy-type SpecimenE636093irradi
45、ation to improve their measuring capabilities. For ex-ample, many early pressurized water reactors (PWR) containwedge-opening loaded (WOL) fracture mechanics specimens.These specimens were originally intended for testing in thebrittle fracture regimen. For ductile materials, bending canoccur in the
46、loading arms of these specimens and the testsbecome invalid. However, techniques have been developed tomake these specimens useful for testing under ductile condi-tions. These include extension of the fatigue precrack ormodification of the specimen dimensions, or both (1). Modifiedspecimen designs m
47、ay be employed for irradiation providedthat it is shown in advance that their use will not significantlydiminish the accuracy of the test or alter test results; ifcorrelations with standard specimen test results have to beemployed, their justification and accuracy have to be provided.6.1.2.1 The pin
48、hole spacings for compact specimens recom-mended in Test Method E 399 and Test Methods E 1820 orE 1921 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 Fatig
49、ue PrecrackingFatigue precracking shall beperformed in accordance with either Test Method E 399, TestMethod E 1820, or Test Method E 1921 as discussed in6.1.3.1-6.1.3.3.6.1.3.1 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 0.55,and precracking should be accomplished in accordance withTest Method E 399 or Test Method E 1921.6.1.3.2 Fully Plastic BehaviorWhen testing is expected tobe perfor
