1. Trang chủ
  2. » Kỹ Thuật - Công Nghệ

Astm stp 888 1986

387 2 0

Đang tải... (xem toàn văn)

Tài liệu hạn chế xem trước, để xem đầy đủ mời bạn chọn Tải xuống

THÔNG TIN TÀI LIỆU

Thông tin cơ bản

Định dạng
Số trang 387
Dung lượng 6,35 MB

Nội dung

The Use of Small-Scale Specimens for Testing Irradiated IVIaterial A symposium sponsored by ASTM Committee E-10 on Nuclear Technology and Applications Albuquerque, N.M., 23 Sept 1983 ASTM SPECIAL TECHNICAL PUBLICATION 888 W R Corwin, Oak Ridge National Laboratory, and G E Lucas, University of California Santa Barbara, editors ASTM Publication Code Number (PCN) 04-888000-35 1916 Race Street, Philadelphia, Pa 19103 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized Libraiy of Congress Cataloging-in-Pnblication Data The Use of small-scale specimens for testing irradiated material (ASTM special technical publication; 888) "A symposium sponsored by ASTM Committee E-10 on Nuclear Technology and Applications, Albuquerque, N.M., 23 Sept 1983." Includes bibliographies and index Materials—Effect of radiation on—TestingCongresses I Corwin, W R II Lucas, Glenn E., 1951III ASTM Committee on Nuclear Technology and Applications IV Series TA418.6.U84 1986 620.1'1228 85-27487 ISBN 0-8031-0440-5 Copyright © by A M E R I C A N S O C I E T Y FOR T E S T I N G AND M A T E R I A L S 1986 Library of Congress Catalog Card Number: 85-27487 NOTE The Society is not responsible, as a body, for the statements and opinions advanced in this publication Printed in Baltimore Md February 1986 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized Foreword The ASTM Symposium on The Use of Nonstandard Subsized Specimens for Irradiated Testing was held in Albuquerque, New Mexico, on 23 September 1983 Its sponsor was ASTM Committee E-10 on Nuclear Technology and Applications W R Corwin, Oak Ridge National Laboratory, and G E Lucas, University of California - Santa Barbara, served as symposium chairmen and have edited this publication The title of this volume has been changed slightly from that of the symposium Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized Related ASTM Publications Effects of Radiation on Materials—12th International Symposium, STP 870 (1985), 04-870000-35 Zirconium in the Nuclear Industry: Sixth International Symposium, STP 824 (1984), 04-824000-35 Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study, STP 819 (1983), 04-819000-35 Creep of Zirconium Alloys in Nuclear Reactors, STP 815 (1983), 04-815000-35 Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects, STP 784 (1982), 04-784000-35 Effects of Radiation on Materials—11th International Symposium, STP 782 (1982), 04-782000-35 Effects of Radiation on Materials—10th International Symposium, STP 725 (1981), 04-725000-35 Irradiation Effects on Structural Alloys for Nuclear Reactor Applications, STP 484 (1971), 04-484000-35 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized A Note of Appreciation to Reviewers The quality of the papers that appear in this publication reflects not only the obvious efforts of the authors but also the unheralded, though essential, work of the reviewers On behalf of ASTM we acknowledge with appreciation their dedication to high professional standards and their sacrifice of time and effort ASTM Committee on Publications Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized ASTM Editorial Staff Allan S Kleinberg Janet R Schroeder Kathleen A Greene Bill Benzing Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized Contents Introduction STRENGTH AND DUCTILITY Use of the Disk Bend Test to Assess Irradiation Performance of Structural Alloys—M L HAMILTON AND F H HUANG Miniaturized Disk Bend Test Technique Development and Application—M P MANAHAN, A E BROWNING, A S ARGON, AND O K H A R L I N G 17 The MTT Miniaturized Disk Bend Test—o K HARLING, M LEE, D-S SOHN, G KOHSE, AND C W LAU 50 Disk-Bend Ductility Tests for Irradiated Materials—R L KLUEH AND D N BRASKI 66 General Discussion: Miniaturized Disk Bend Test 83 Development of Small Punch Tests for Ductile-Brittle Transition Temperature Measurement of Temper Embrittled Ni-Cr Steels—J.-M BAIK, I KAMEDA, AND O BUCK 92 Discussion 110 Shear Punch and MScrohardness Tests for Strength and Ductility Measurements—G E LUCAS, G R ODETTE, AND I W SHECKHERD 112 Discussion 139 Low-Load Microhardness Changes in 14-MeV Neutron Irradiated Copper Alloys—s i ZINKLE AND G L KULCINSKI Discussion Copyright Downloaded/printed University 141 159 by by of Effects of Specimen Thickness and Grain Size on the Mechanical Properties of Types 304 and 316 Austenitic Stainless Steel— N IGATA, K MIYAHARA, T UDA, AND S ASADA 161 Failure Strain for Irradiated 2^aloy Based on Subsized Specimen Testing and Analysis—R B ADAMSON, S B WISNER, R P TUCKER, AND R A RAND 171 Discussion 185 Wire Tensile Testing for Radiation-Hardening Experiments— E R BRADLEY AND R H JONES 186 Discussion 200 D e s ^ and Use of Nonstandard Tensile Specimens for Irradiated Materials Testing—N F PANAYOTOU, S D ATKIN, R J PUIGH, A N D B A C H I N 201 Discussion 219 Comparison of Mechanical Properties in Thin Specimens of Stainless Steel with Bulk Material Behavior—D G RICKERBY, P FENICI, p JUNG, G PIATTI, A N D P SCHILLER 220 Discussion 231 A Miniaturized Mechanical Testing System for Small-Scale Specimen Testing—S.-P HANNULA, J WANAGEL, AND C.-Y LI 233 Discussion 250 Post-Irradiation Creep Properties of Cold-Worked 316 Stainless Steel As Measured with Small Creep Specimens— w VANDERMEULEN, M SNYKERS, AND PH VAN ASBHOECK 252 FATIGUE AND FRACTURE Miniature Center-Cracked-Tension Specimen for Fatigue Crack Growth Testhig—A M ERMI AND L A IAMES 261 Use of Subsize Fatigue Specimens for Reactor Irradiation Testing— K C LIU AND M L GROSSBECK 276 Discussion 289 Use of Subsized Specimens for Evaluating the Fracture Toughness of Irradiated Materials—F H HUANG Discussion Copyright Downloaded/printed University 290 303 by by of Subsized Bend and Charpy V-Notch Specimens for Irradiated Testing—G E LUCAS, G R ODETTE, I W SHECKHERD, p M C C O N N E L L , A N D I PERRIN 305 Discussion 324 Effect of Specimen Size and Material Condition on the Charpy Impact Properties of 9Cr-lMo-V-Nb Steel—w R CORWIN AND A M HOUGLAND 325 Discussion 337 Specimen-Size Considerations in Craclc-Arrest Testing of Irradiated RPV Steels—c w MARSCHALL, A R ROSENFIELD, AND M p LANDOW 339 Experience in Subsized Specimen Testing—p MCCONNELL, J W S H E C K H E R D , J S PERRIN, AND R A WULLAERT 353 Summary 369 Index 371 Copyright Downloaded/printed University by by of 366 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL T6MPERATUHE fC) " SO 1 150 1 1 RECONSTITUTED CVN - IRRADIATED SUBMERGED ARC WELD METAL (SA508-2 BASE) o ORIGINAL SPECIMEN * t „ , „ ^ a 1.1 x " n / c m ^ - A RECONSTITUTED SPECIMEN, e t , , i „ „ ^ s 0.85 x 10' o o """o - - o 1 1 i 1 160 I i 250 i 360 1 1 1 TEMPERATURE CFI TEMPERATURE C O -150 -50 50 1 150 1 3! 260 I RECONSTITUTED CVN - IRRADIATED SUBMERGED ARC WELD METAL (SA50-2 BASE) 60 - o ORIGINAL SPECIMEN, » t , „ „ g , a 1.1 X l o " nlcm^ - A RECONSTITUTED SPECIMEN, o t , „ „ , „ a a 0.85 x 10' o s ^ o & - o 40 i 40 - 20 y A 1 1 1 ! 150 1 i 250 350 1 1 1 TEMPERATURE CF] FIG 9—Comparison of Charpy V-notch data from reconstituted and original specimens of irradiated submerged arc weld material Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authoriz McCONNELL ET AL ON SUBSIZED SPECIMEN TESTING 367 i / ^ ^ % ^ '/M^ r^ \^ ^^' c^^H.b'^x^ / ^ "' v ^ CZ I D FIG 10—Procedure for reconstructing a Charpy specimen using mechanical tabs maul et al [12] The technique consists of taking a small cylinder of material in short supply (such as an irradiated Charpy) and electron beam welding that material into the critical region (crack zone) of another piece of material with the nominal dimensions of a compact specimen Such specimens were termed compound by the works cited Originally compacts 25 to 150 mm were fabricated using cylinders of test material 20 to 100 mm in diameter However, much smaller pieces (5 to mm diameter) could be electron beam welded without changes in metallurgical structure This technique proved successful for fabricating fracture toughness specimens as well as tension (flat and round specimens) and Charpy V-notch specimens Conclusion A variety of techniques utilizing subsized specimens for obtaining critical data, particularly for irradiation studies, has been reviewed Most of these techniques were successful in generating the desired data Of particular note is the use of very small compact specimens (approximately mm thick) to obtain a valid fracture toughness fibrous crack growth resistance curve which may be used as a design parameter Although miniature Charpy specimens provide only empirical, or qualitative, correlation to the standard size specimen results, they nonetheless are practical The miniature Charpy data are particularly useful for tracking irradiation behavior or monitoring relative difference of materials Means of reconstructing specimens have been developed Notable are standard sized Charpy specimens made for small pieces of broken specimens Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized 368 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL These methods attest to the viability of generating relevant data when economy of material is essential References [/] Wilkins, M L., Streit, R D., and Reaugh, J E., "Cumulative-Strain-Damage Model of Ductile Fracture Simulation and Prediction of Engineering Fracture Tests," Report UCRL-53058, Lawrence Livermore National Laboratory, Livermore, Calif., Oct 1980, [2] Ernst, H A., "Material Resistance and Instability Beyond i-Controlled Crack Growth," Westinghouse Report 81-1D7-JINTF-P6, Westinghouse R&D Center, Pittsburgh, Dec 198L [,7| Nelson, F G and Kaufman, ] G., "Fracture Toughness of Plain and Welded 3-In.-Thick Aluminum Alloy," in Flaw Growth and Fracture Toughness Testing, ASTM STP 536, American Society for Testing and Materials, Philadelphia, 1972, pp 350-376 \4] C F Shih and J P Gudas, Eds., Elastic-Plastic Fracture: Second Symposium (2 volumes), ASTM STP 803 American Society for Testing and Materials, Philadelphia, 1983 [5| R J Sanford, Ed., Fracture Mechanics: Fifteenth Symposium, ASTM STP 833 American Society for Testing and Materials, Philadelphia, 1984 [6] Ohtsuka, N., "Influence of Specimen-Thickness and Side-Grooves on 7|c Tests," Transactions of Japanese Society of Mechanical Engineers No 810-7, 1981, pp 119-124 [ 7| Grounes, M., "Review of Swedish Work on Irradiation Effects in Pressure Vessel Steels and on Significance of Data Obtained," in Effects of Radiation on Structural Metals, ASTM STP 426 American Society for Testing and Materials, Philadelphia, 1967, pp 224259 [S] Lucas, G E et al, "Subsized Bend and Charpy V-Notch Specimens for Irradiated Testing," this publication, pp 305-324 [9] Shabbits, W O., "Dynamic Fracture Toughness Properties of Heavy Section A533B-1 Steel Plate," Westinghouse Report WCAP-7623, Pittsburgh, Dec 1970 [10] Perrin, J S et al, "Preparation of Reconstituted Charpy V-Notch Impact Specimens for Generating Pressure Vessel Steel Fracture Toughness Data," in Effects of Radiation on Materials: Eleventh Conference, ASTM STP 782 American Society for Testing and Materials, Philadelphia, 1982, pp 582-593 / / ] Perrin, J S et al, "Reconstructed Charpy Impact Specimens," Report NP-2759, Electric Power Research Institute, Palo Alto, Calif., Dec 1982 [12] Kussmaul, K., Vetz, H., and Kuri, M., "Production of Compound Fracture Toughness Specimens to Enable a Large CT Specimen to be Made from a Small Sample Volume," InternationalJournal of Pressure Vessels and Piping Vol 5, 1977, p 152 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized STP888-EB/Feb 1986 Summary As was indicated in the Introduction, and as is evident in the body of papers contained in this ASTM Special Technical Publication, a large variety of small-specimen techniques has been under development; and these offer an opportunity to extract a wide range of mechanical properties Certainly, not all of the investigators involved in small-specimen research were able to contribute to this publication; however, the papers herein are representative of the types of progress being made Development efforts to date appear to fall roughly into two categories: (1) those which are based on a miniaturization or scaling down of what might be termed "conventional" test specimens, and (2) those which are based on novel, unconventional techniques The first category includes such techniques as miniature tensile, fatigue, fatigue crack growth, impact, and fracture toughness tests Corresponding specimens currently have a wide range of volumes, from the crack arrest toughness specimens (~ 25 cm-*) reported by Marshall et al down to the small wire tensile specimens (~ mm^) reported by Bradley and Jones These specimens are all, of course, small relative to their conventional counterparts The second category of tests, such as disk bend, punch, and ball microhardness, is largely directed towards extracting properties from transmission electron microscopy (TEM) disks or TEM disk-sized specimens (~1.7 mm-') Many of the tests in both categories have already been applied to extract useful qualitative or quantitative mechanical property data from irradiated specimens, but further miniaturization and/or development may be warranted in individual cases Moreover, a number of tests provide similar kinds of data (e.g., strength or ductility parameters) using considerably different approaches As these tests mature, however, it is likely that natural selection processes will result in the consolidation and elimination of complementary and duplicative techniques, respectively Not surprisingly, current small-specimen techniques address most of the properties considered of major interest for fusion reactor materials development A number of extensions could be made using existing or slight modifications of existing techniques to obtain additional properties of interest, such as multiaxial ductility parameters or threshold fatigue crack propagation This remains a goal for future research In addition, there still appear to be opportunities for developing new test techniques to extract properties which are not currently being addressed; for instance, small-scale environmentally assisted cracking test specimens may be quite useful Another area requiring 369 Copyright by Copyright 1986 Downloaded/printed University of ASTM by Washington Int'l b y A S T M International (all www.astni.org (University rights of reserved); Washington) Thu pursuant Dec 31 to Licen 370 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL further attention is technique automation, since alloy development programs ultimately will, and do, require rapid testing of large numbers of specimens Nonetheless, major inroads have been made in small-specimen testing Existing techniques have very promising applications not only in developing materials for fusion reactors, but in numerous situations in both nuclear and non-nuclear systems where constraints require the extraction of mechanical properties from small-volume specimens W R Corwin Metallurgical Engineer, Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee; symposium chairman and editor G E Lucas Associate Professor, Department of Chemical and Nuclear Engineering, University of California, Santa Barbara, California; symposium chairman and editor Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized STP888-EB/Feb 1986 Author Index L-M A-B Adamson, R B., 171 Argon, A S., 17 Asada, S., 161 Atkin, S D., 201 Baik, J.-M., 92 Bradley, E R., 186 Braski, D N., 66 Browning, A E., 17 Buck, O., 92 Landow, M P., 339 Lau, C W., 50 Lee, M., 50 Li, C.-Y., 233 Liu, K C , 276 Lucas, G E , 1, 112,305,369 Manahan, M P., 17 Marschall, C W., 339 McConnell, P., 305, 353 Miyahara, K., 161 C-H Chin, B A., 201 Corwin, W R., 1, 325, 369 Ermi, A M., 261 Fenici, P., 220 Grossbeck, M L., 276 Hamilton, M L., Hannula, S.-P., 233 Harling, O K., 17, 50 Hougland, A M., 325 Huang, F H., 5, 290 O-R Odette, G R., 112, 305 Panayotou, N F., 201 Perrin, J S., 305, 353 Piati, G., 220 Puigh, R J., 201 Rand, R A., 171 Rickerby, D G., 220 Rosenfield, A R., 339 I-K Igata, N., 161 James, L A., 261 Jones, R Hi, 186 Jung, P., 220 Kameda, J., 92 Klueh, R L., 66 Kohse, G., 50 Kulcinski, G L., 141 S-U Schiller, P., 220 Sheckherd, J W., 112, 305, 353 Snykers, M., 252 Sohn, D.-S., 50 Tucker, R P., 171 Uda, T., 161 371 CopyrightCopyright' by ASTM1986 Int'lb (all rights reserved); Thu Dec 31 17:50:21 EST 2015 y A S T M International www.astni.org Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized 372 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL V-Z ,, , I ni i n Van Asbroeck, Ph., 252 Wisner, S B., 171 Wullaert, R, A., 353 ' ' ,, Z i n k l e , S J., 141 J ,,r TCT Vandermeulen, W., 252 Wanagel, J., 233 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized STP888-EB/Feb 1986 Subject Index Aging of steel {see Steel, aging of) Alignment disk bend test, 83 wire tensile test, 186 Alloys A286 steel, 290 A302B steel, 308 A508 steel, 308 A533B-based steel, 308 aluminum, 6061-T651, 353 chromium-molybdenum-vanadium-niobium steel, 325 copper-aluminum, 141 copper-beryllium, 112 copper-manganese, 141 copper-nickel, 141 copper-nickel-beryllium, 206 HT-9 steel, 206, 290, 305 molybdenum-modified steel, nickel-base steel, nickel-chromium steel, 92 niobium-modified steel, Path B steel, Zircaloy, 171 Aluminum, 141, 353 Aspect ratio (AR), 27, 85 ASTM Cooperative Test Program, 345 ASTM Standards E9: 360 E23: 328 E178: 146 E208: 341 E399: 318 E606: 276 E647: 261, 268 E813: 355 ASTM Subcommittee E10.02: Behavior and Use of Metallic Materials in Nuclear Systems, Axisymmetric loading, B Ball microhardness test (see Microhardness tests) Beam interference microscopy, 122, 123-124, 127-130 Bench marking, disk bend test, 86, 88 Beryllium, 112, 206 Biaxial loading, 23, 107, 174 Brass, 132 Breeder reactors (see Reactors, breeder) Buckling of test specimens, 85, 261, 276 Bulk material behavior (see Macrobehavior versus small-scale specimen behavior) Center-cracked tension specimen ASTM Standard E 647: 261 Charpy V-notch specimen, 92, 305, 325, 353 rebuilding of, 361 373 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized 374 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL Chromium, 5, 67, 92, 311, 325 Closed-end bulge/burst specimen, 174 Cold-worked steel (see Steel, coldworked) Compact tension specimen, 253, 290, 353 ASTM Standard E 813: 355 rebuilding of, 361 Compound specimen, 261, 353 Compression specimen ASTM Standard E 9: 360 Copper, 112, 141, 206,241 Crack arrest (see Crack growth; Fracture toughness test) Crack growth in alloys A286/HT-9, 290 in center-cracked tension specimen Type 304 steel, 261 in Charpy V-notch specimens A302/A508/A533B-based steel, 305 in compact tension specimen Type 316 steel, 290 fatigue tests, 59 in notched specimen nickel-chromium steel, 92 Type 316 steel, 220 pre-cracking effects, 290, 305 in reactor pressure vessel steels, 305, 339 three-point bend specimens, A302/A508/A533B-based steel, 305 thin specimens, Type 316 steel, 220 Crack initiation, 220 Crack propagation (see Crack growth) Crack tip, rebuilt specimens, 353 Creep properties Type 316 steel, 220, 252 Curvilinear tensile specimen, 174 D Data processing, 22, 87, 117, 271, 307 (see also Finite element analysis) Deformation in disk bend tests, 84-85 in microhardness test, 112 Disk bend tests (see also Electron microscopy, disks) apparatus diagrams, 8, 20, 52, 68 applications, potential, 88, 91 buckling of disk, 85 centering of disk, 83 disk preparation, 23 fatigue, 59 MIT developed, 17, 50 of Path B alloys, of Type 316 steel, 17, 50 of Type 446 ferritic steel, 66 summary of status, 89 Dislocation channeling, 171 Dislocation loops, 141 Displacement rate tests, 233 Ductile-brittle transition temperature A302B/A508 steels, 305 A533B-based steel, 305 ASTM Standard E 208:341 9Cr-lMo-V-Nb steel, 325 Ni-Cr steel, 92 Type 302 steel, 50 Type 410 steel, 63 Ductility irradiated steel, 5, 17, 50, 66 irradiated Zircaloy, 171 Path B alloys, table, 10 Duplex specimens, 351 E Electrical discharge machining (EDM), 17, 175, 355 Electrical potential monitoring, 261 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized SUBJECT INDEX Electron microscopy disks, 5, 17, 50, 66, 112, 141 photos crack growth, M30-200-Sn steel, 101 crack initiation, A533B steel, 319 disk bend test specimens, 25, 64, 72-74, 76, 77 dislocation channels, Zircaloy, 181 fractures, Type 304 steel, 166 indentation, copper-beryllium alloy, 125, 126 stretch zone, A302B steel, 314 tapered gage, titanium wire, 192 Electropolishing, 186 table, 191 Elongation, 161, 171, 186, 201, 220, 252 Embrittlement (see also Ductilebrittle transition temperature) radiation-induced, 66 thermal-induced, 92, 325 Energy, lower/upper shelf, 305, 325 Expanding mandrel specimen, 174 375 Ductile-brittle transition temperature) Fracture energy transition curves, 101, 102 Fracture toughness tests aluminum, 6061-T651, 353 apparatus, 293, 308, 342 ASTM Standard E 813, 355 steels A286 alloy, 290 9Cr-lMo-V-Nb, 325 HT-9 alloy, 290, 305 reactor pressure vessels, 325 Type 316, 290 Fusion reactors (see Reactors, nuclear fusion) Grain size effect on ductile-brittle transition temperature Ni-Cr steel, 92 effect on mechanical properties Types 304/316 steel, 161 effect on tensile properties nickel, niobium, vanadium, and titanium wires, 186 H Fatigue crack growth (see Crack growth) Fatigue testing (see Disk bend tests, fatigue; Thermal fatigue) Fermi-type specimens, 208 Finite element analysis disk bend tests, 17, 50, 83, 87-88 fracture toughness tests, 354 simulation, load/deflection curves, 17 Flaws, reactor pressure vessels, 305 Fracture, brittle, 92 (see also Crack growth; Crack initiation; Hall-Petch relation, 161 Hanford Engineering Development Laboratory (HEDL), 66 Helium, irradiated Path B alloys, table, I Impact energy data, 353 Indentation geometry, microhardness test, 112, 141 Indentation hardness tests, 233 apparatus diagram, 238 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized 376 SMALL-SCALE SPECIMENS FOB TESTING IRRADIATED MATERIAL Instron tensile testing machine, 61, 186, 292 Interferography differential interference, 123-124, 127, 129 multiple beam, 122, 130 Irradiation effect on creep properties Type 316 steel, 252 effect on ductility Path B/nickel-base alloys, Type 446 steel, 66 effect on fracture toughness aluminum, 6061-T651, 353 Type 316 steel, 290 effect on mechanical properties copper alloys, 112 Type 302 steel, 50 Type 316 steel, 220 effect on microhardness, copper alloys, 112, 141 effect on plane strain/stress, Zircaloy, 171 effect on reactor pressure vessel steels, 339, 359 effect on tensile properties nickel, niobium, vanadium, and titanium wires, 186 Type 316 steel wires, sheet specimens, 201 copper-nickel beryllium/ HT-9 alloy sheet specimens, 201 effect on thermal fatigue Type 316 steel, 276 /-integral, 290, 305, 354 K Knoop microhardness, 27 Lapping, precision machine, 23 Linear elastic fracture mechanics (LEFM), 21 Load deflection curves, 9, 53-56, 60, 70, 72-74, 99-100 Load relaxation tests, 233 Loads axisymmetric, 5, 83 biaxial, 23, 66, 107, 174 central, 17 compressive, 233 cyclic, 233, 276 fatigue, 276 indentation, 141 low level, 141 transverse wedge, 342 uniaxial tensile, 233 M Machining, electrodischarge (see Electrical discharge machining) Macrobehavior versus small-scale specimen behavior crack arrest tests, 339 disk bend tests bench marking, 86, 88 finite element analysis, 36 fatigue crack growth, 220 fracture toughness, 353 impact tests, 325 load relaxation tests, 233 microhardness tests, 141 tensile properties tests, 201, 220, 233 table, 178 thermal creep tests, 220 thermal fatigue tests, 276 Manganese, 66, 141 Massachussets Institute of Technology (MIT), 17, 50 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized SUBJECT INDEX Matrix hardening, Mechanical properties disks chromium-molybdenum, 66 copper-beryllium, 112 Type 316 steel, 17, 50 Type 446 steel, 66 nuclear reactor components, Zircaloy, 171 thin foil specimens Type 304/316 steel, 161 thin specimens Type 316 steel, 220 thin wires copper, 233 various metals, 186 Microhardness test antivibration stand, 144 apparatus diagram, 115 copper/copper alloys, 112, 141 Microstructure (see also Electron microscopy, photos; Interferography) brass, 132 copper-nickel-beryllium (alloy 3), 215 disks, electron microscopy, 26, 90 HY-9 steel, 214 Path B alloys, Type 316 steel, 23, 213 Miniaturized disk bend test (MDBT) (see Disk bend test) Molybdenum, 5, 325 N Neutrons Be, 186 14-MeV, 112, 114, 220 T, 186 Nickel, 186 in copper alloys, 141, 206 in steel alloys, 5, 67, 92, 206 Niobium, 7, 186, 325 377 Notched specimens, 92, 220, 261, 339 (see also Charpy V-notch specimen) Nuclear fusion reactors (see Reactors, nuclear fusion) O Optical comparator, 83 Optical metallography, 140 Parameters, fracture mechanic, 305 Photomicrographs (see Electron microscopy, photos) Plane strain, 174, 342 Plasticity disks, electron microscopy, 85 welded steel specimens, 264 Press-fit specimens, 361 Pressure vessels, 305, 339, 353 Protons, 16-MeV, 186 Punch tests, 92, 112 apparatus diagram, 95, 131 Punching, specimen production, 201 R Radiation hardening, 186 /?-curve analysis, 299 Reactors breeder, 5, 291 components, table, 173 nuclear fusion, 1, 66, 112, 261, 276, 305, 353 pressure vessels, 305, 339, 353 Rebuilt specimens Charpy V-notch, 361 compact tension, 361 Reproducibility band, 84 Rupture time, creep specimens, 254 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized 378 SMALL-SCALE SPECIMENS FOR TESTING IRRADIATED MATERIAL ferritic, 66, 92, 305, 325 HT-9, 290 Scanning electron microscopy {see Linde 009, 308 Electron microscopy) martensitic, 305 Shear punch test, 112 microstructure of, 23, 90, 92, 166, Sheet-type tensile specimen, 201, 220 314,319 Sideband tensile specimen, 174 nickel-chromium alloys, 92 Specimens P-doped, 94 center-cracked tension, 261 pressure vessel, 305, 339 Charpy V-notch, 92, 305, 325, Sn-doped, 94 353, 361 stainless, 17, 50, 66,161, 201, 220, closed-end bulge/burst, 174 233, 252, 276, 290 compact tension, 253, 290, 353 Type 302, 50, 85 compound, 261, 353 Type 304, 161 compression, 360 Type 316, 17, 23, 161, 201, 220, curvilinear tensile, 174 233, 252, 276, 290 disks, transmission electron miType 446, 66 croscopy, 5, 17, 50, 66 Strain duplex, 351 disk bend tests, 86 expanding mandrel, 174 model development, 354 Fermi-type, 208 plane type, 171 geometry of, 327 small punch tests, 92 table, 174 Stress {see also Loads) notched, 92, 220, 261, 339 axisymmetric, press-fit, 361 flow type, 115 rebuilt microcleavage fracture, 311 Charpy V-notch, 361 uniaxial tensile, 89, 112 compact tension, 361 yield, 80, 112, 220 sheet-type tensile, 201, 220 0.2% proof strength, 161 sideband tensile, 174 Stretch zone analysis, 313 thin foil, 161 Subsized specimens geometry, 174three-point bend, 174, 305 175 welded, 261 Surface softening, copper/copper alwire tensile, 186, 233 loys, 141 Stainless steel {see Steel, stainless) Surveillance, nuclear reactors, 253 Steel A286, 290 A302B, 308 TEM disks {see Electron microA508, 308 scopy, disks) A533B-based, 308 Temperature {see also Ductile-brittle aging of, 5, 67, 92, 252, 310 transition temperature) austenitic (see Steel, stainless) elevated cold-worked, 5, 206, 252, 290 aging of steel {see Steel, aging of) 9Cr-lMo-V-Nb alloy, 325 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authorized SUBJECT INDEX effect on A286 steel alloy, 290 effect on Charpy V-notch steel specimens, 305 effect on nickel-base steel alloys, effect on reactor pressure steels, 347 effect on three-point bend steel specimens, 305 effect on Type 304 steel, 261 effect on Type 316 steel, 220, 276, 290 effect on Zircaloy, 171 lowered effect on crack arrest, reactor pressure vessels, 347 room effect on copper, 233 effect on Type 316 steel, 233 effect on Type 446 steel, 70 Temperature control equipment, 240 Tensile tests {see Instron tensile testing machine; Ultimate tensile strength; Uniaxial tensile behavior; Wire tensile tests ) Thermal creep tests (see Creep tests) Thermal fatigue, 276 apparatus diagram, 279, 283 Thickness, steel specimens, 161, 220, 261 Thin foil specimen, 161 Three-point bend specimen, 174, 305 Tin, 101 Titanium, 186 Tools for subsize specimens, 283 Transmission electron microscopy (see Electron microscopy) Two-parameter criteria, 305 379 Uniaxial tensile behavior biaxial tensile behavior comparison, 107 disk bend test comparison, 17, 38, 66,89 punch test comparison, 92, 107 table of test comparisons, 171 thin wire testing, 233 U.S Fusion Program, Vacuum, 220, 276 Vanadium, 186, 325 Vibration control equipment, 141, 240 Vickers microhardness test, 141 W Welded specimens, 261 Wire tensile tests, 186, 233 apparatus diagrams, 188, 193, 235, 238 Work hardening, 112, 161, 186 Yield strength crack growth, steel, 311, 344 indenter loads, copper/copper alloys, 141 sheet specimens, steel, 201 tensile loads, wire, 186 thin specimens, steel, 220 U Ultimate tensile strength, 112, 161, 201, 220 Zircaloy, 171 Zirconium, 171 Copyright by ASTM Int'l (all rights reserved); Thu Dec 31 17:50:21 EST 2015 Downloaded/printed by University of Washington (University of Washington) pursuant to License Agreement No further reproductions authoriz

Ngày đăng: 12/04/2023, 16:39