1、Designation: E 636 02Standard 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 (e) 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,
3、those required byPractice E 185 for the surveillance of nuclear reactor vessels.The supplemental mechanical property tests outlined permitthe acquisition of additional information on radiation-inducedchanges in fracture toughness, notch ductility, and tensilestrength properties of the reactor vessel
4、 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 given. Ref
5、er-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:E 8 Test Methods for Tension Testing of Metallic Materials2E23 Test Methods for Notched Bar Impact Testing ofMetallic Materials2E 184 Practice f
6、or Effects of High-Energy Neutron Radia-tion on the Mechanical Properties of Metallic Materials,E 706 (IB)3E 185 Practice for Conducting Surveillance Tests for LightWater Cooled Nuclear Power Reactor Vessels, E 706 (IF)3E 399 Test Method for Plane-Strain Fracture Toughness ofMetallic Materials2E 482
7、 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance, E 706 (IID)3E 560 Practice for Extrapolating Reactor Vessel Surveil-lance Dosimetry Results, E 706 (IC)3E 616 Terminology Relating to Fracture Testing2E 706 Master Matrix for Light-Water Reactor PressureVessel Survei
8、llance Standards, E 706 (0)3E 1221 Test Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, K1a, of Ferritic Steels2E 1253 Guide for Reconstitution of Irradiated Charpy-SizedSpecimens3E 1820 Test Method for Measurement of Fracture Tough-ness3E 1921 Test Method for Determination of R
9、eference Tem-perature, T0, for Ferritic Steels in the Transition Range32.2 Other Standards:ASME Boiler and Pressure Vessel Code, Section III, Sub-section NB (Class 1 Components)4ISO 14556 Steel Charpy V-notch Pendulum Impact Test-Instrumented Test Method53. Significance and Use3.1 Practice E 185 des
10、cribes a minimum program for thesurveillance of reactor vessel materials, specifically mechani-cal property changes that occur in service. Guide E 636 may beapplied in order to generate additional specific fracture tough-ness property information on radiation-induced propertychanges to better assist
11、 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 specimen duringwhich a record of force versus displacement is used todetermine material fract
12、ure 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 E 399, E 1820, and E 1921, respec-tively). These test methods generally apply to elastic, elastic-plastic, or fully pl
13、astic behavior. The rate of specimen loadingor stress intensity increase required for test classification asstatic or dynamic is indicated by the referenced test methods.Presently, only Test Methods E 399 and E 1820 specify a lowerlimit on loading rate for dynamic test performed in the linearelastic
14、 regime.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.Current edition approved June 10, 2002. Published September 2002. Originallypublished a
15、s E 636 83. Last previous edition E 636 95.2Annual Book of ASTM Standards, Vol 03.01.3Annual Book of ASTM Standards, Vol 12.02.4Available from American Society of Mechanical Engineers, 345 E. 47th St.,New York, NY 10017.5Available from International Organization for Standardization (ISO), 1 rue deVa
16、rembe, Case postale 56, CH-1211, Geneva 20, Switzerland.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.4.2 Precracked Charpy Impact TestThis test involvesimpact testing of Charpy V-notch specimens that have beenfatigue precracked. A
17、 force versus deflection or time record, orboth, are obtained during the test to determine an estimate ofmaterial dynamic fracture toughness properties. The testmethod applies to the brittle/ductile transition region. Cur-rently, no standard test method is available for performing andanalyzing this
18、test; details on the recommended procedures aregiven in 7.1 7.4 and Appendix X1.4.3 Instrumented Charpy V-Notch TestThis test involvesthe impact testing of standard Charpy V-notch specimens usinga conventional tester (Test Methods E23) equipped withsupplemental instrumentation that provides a load v
19、ersusdeflection or time record, or both, to augment standard test data( ISO 145556). The test 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 s
20、not covered byASTMstandards, 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. However, the user should establish themethods technical validity and
21、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 location of plate and forging materials, as defined inNB 2300 of ASME C
22、ode Section III, and at a distance at leastone material thickness from a quenched edge. Specimens fromnear surface material also may be considered for specialstudies, if required. For weld deposits, it is recommended thatthe specimens be taken from a thickness location at least 12.7mm (12 in.) remov
23、ed from the root and the surfaces of theweld. Consistent with Practice E 185, it is further recom-mended that the specimens be oriented to represent thetransverse orientation (T-L, per Test Method E 399) in plateand forging materials. Specimens having the longitudinalorientation (L-T, per Test Metho
24、d E 399) also may be usedgiven sufficient material and space in the surveillance capsule.For weld deposits, the specimen shall be oriented to make theplane of fracture parallel to the welding direction and perpen-dicular to the weldment surface, with the direction of crackgrowth along the welding di
25、rection. Examples of specimenorientations 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 at the approximate weld deposit centerline. Thece
26、nterline 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. The general appearance of the etched weld deposit
27、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, and documentation system shall be usedwhereby the location and orientation of each specime
28、n 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 PreparationAll specimens shall be prepared frommaterial that has been fully heat-treated, including
29、 stress-reliefannealing, as recommended in Practice E 185.5.1.2.1 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 proc
30、edure has no significant influence on thefracture toughness test result.FIG. 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 OrientationE6360225.1.2.
31、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 PrecrackingIt is recommended that fa-tigue precracking of specimens, if required, should be accom-plished prior
32、 to irradiation to avoid difficulties of precrackingfollowing irradiation. However, fatigue precracking of a speci-men following irradiation is acceptable if a suitable means offollowing crack extension in the specimen is established.5.1.2.4 Fatigue Precracking of Postirradiation Heat-Treated Specim
33、ensSome postirradiation heat treatments attemperatures higher than the prior irradiation exposure cancause mechanical property recovery, including reductions inyield strength and tensile strength and an improvement infracture toughness toward preirradiation levels. Compliancewith Test Methods E 399,
34、 E 1820, and E 1921, 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 treatment typical of reactorvessel annealing. I
35、t is believed that heat treatments of ferriticmaterials below 482C (900F) do not alter the test results andthat the fatigue precracked tests represent the bulk materialproperties as intended.5.2 Specimen Irradiation:5.2.1 GeneralThe recommendations of Practice E 185concerning the encapsulation of sp
36、ecimens, 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 individualspecimens and within the specimen
37、 capsules.5.2.2 Specimen IrradiationSupplemental test specimensmay be irradiated in the same capsule as the specimensrequired 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,
38、 remote devices for accurately positioning thespecimen in the test machine are generally required. Fornotched or precracked impact specimens, automatic devices toposition the specimen on the test anvils are strongly recom-mended. Additional remote devices for specimen heating andcooling and for the
39、attachment of measuring fixtures are alsonecessary. Remote testing equipment shall satisfy the toler-ances and 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
40、performed inaccordance with Practice E 185 prior to supplemental speci-men testing to establish a basis for selecting test temperaturesfor the supplemental specimens provided under this method.5.5 Documentation:5.5.1 The report shall include the reporting requirements onmaterial identification and i
41、rradiation history required byPractice E 185. 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 be reported.Any special modificat
42、ions (for example, load 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 Prac-tice E 185, including data from
43、 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 reconstitution technique shall be given inacco
44、rdance with Guide E 1253.6. 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 E 399, Test Method E 1820, or Test Method E 1921,allowing for design modification (see 6.
45、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-type is illus-trated in Fig. 2.
46、Specimens have also been modified afterirradiation to improve their measuring capabilities. For ex-ample, many early PWR reactors contain WOL size fractureFIG. 2 Various Forms of End-Tab Welded (Compound) SpecimensE636023mechanics specimens. These specimens originally were in-tended for testing in t
47、he brittle fracture regimen. For ductilematerial, bending can occur in the loading arms of thesespecimens and the tests become invalid. However, techniqueshave been developed to make these specimens useful fortesting under ductile conditions. These include extension of thefatigue precrack length or
48、modification of the specimen dimen-sions, or both (1). Modified specimen designs may be em-ployed for irradiation provided that it is shown in advance thattheir use will not significantly diminish the accuracy of the testor alter test results; if correlations with standard specimen testresults have
49、to be employed, their justification and accuracyhave to be provided.6.1.2.1 The pinhole spacings for compact specimens recom-mended in Test Method E 399 and Test Method E 1820 aredifferent. However, this difference does not significantly affectthe stress field at the crack tip and therefore either pinholespacing is acceptable for surveillance testing (2).6.1.3 Fatigue 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-Pl
