ASTM E636-2002 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对E706(IH)核动力反应堆压力容器进行辅助监视试验的标准指南》.pdf
《ASTM E636-2002 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对E706(IH)核动力反应堆压力容器进行辅助监视试验的标准指南》.pdf》由会员分享,可在线阅读,更多相关《ASTM E636-2002 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels E 706 (IH)《对E706(IH)核动力反应堆压力容器进行辅助监视试验的标准指南》.pdf(9页珍藏版)》请在麦多课文档分享上搜索。
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
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