1、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-
2、Santa Barbara,editors ASTM Publication Code Number(PCN)04-888000-35 1916 Race Street,Philadelphia,Pa.19103 Copyright by ASTM Intl(all rights reserved);Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washington(University of Washington)pursuant to License Agreement.No further reproduct
3、ions 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 bibli
4、ographies and index.1.MaterialsEffect of radiation onTesting-Congresses.I.Corwin,W.R.II.Lucas,Glenn E.,1951-III.ASTM Committee on Nuclear Technology and Applications.IV.Series.TA418.6.U84 1986 620.11228 85-27487 ISBN 0-8031-0440-5 Copyright by AMERICAN SOCIETY FOR TESTING AND MATERIALS 1986 Library
5、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 Intl(all rights reserved);Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washing
6、ton(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 Techno
7、logy and Ap-plications.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 Intl(all rights reserved)
8、;Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washington(University of Washington)pursuant to License Agreement.No further reproductions authorized.Related ASTM Publications Effects of Radiation on Materials12th International Symposium,STP 870(1985),04-870000-35 Zirconium in the Nu
9、clear Industry:Sixth International Symposium,STP 824(1984),04-824000-35 Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Ves-sels: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 React
10、or Pressure Vessel Surveillance for Radiation Effects,STP 784(1982),04-784000-35 Effects of Radiation on Materials11th International Symposium,STP 782(1982),04-782000-35 Effects of Radiation on Materials10th International Symposium,STP 725(1981),04-725000-35 Irradiation Effects on Structural Alloys
11、for Nuclear Reactor Applications,STP 484(1971),04-484000-35 Copyright by ASTM Intl(all rights reserved);Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washington(University of Washington)pursuant to License Agreement.No further reproductions authorized.A Note of Appreciation to Revie
12、wers 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
13、 time and effort.ASTM Committee on Publications Copyright by ASTM Intl(all rights reserved);Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washington(University of Washington)pursuant to License Agreement.No further reproductions authorized.ASTM Editorial Staff Allan S.Kleinberg Jane
14、t R.Schroeder Kathleen A.Greene Bill Benzing Copyright by ASTM Intl(all rights reserved);Thu Dec 31 17:50:21 EST 2015Downloaded/printed byUniversity of Washington(University of Washington)pursuant to License Agreement.No further reproductions authorized.Contents Introduction STRENGTH AND DUCTILITY U
15、se of the Disk Bend Test to Assess Irradiation Performance of Structural AlloysM.L.HAMILTON AND F.H.HUANG 5 Miniaturized Disk Bend Test Technique Development and ApplicationM.P.MANAHAN,A.E.BROWNING,A.S.ARGON,AND O.K.HARLING 17 The MTT Miniaturized Disk Bend Testo.K.HARLING,M.LEE,D-S SOHN,G.KOHSE,AND
16、 C.W.LAU 50 Disk-Bend Ductility Tests for Irradiated MaterialsR.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 SteelsJ.-M.BAIK,I.KAMEDA,AND O.BUCK 92 Discussion 110 Shear Punch and MScrohardness Tests for Strength and Ductility MeasurementsG.E.LUCAS,G.R.ODETTE,AND I.W.SHECKHERD 112 Discussion 139 Low-Load Microhardness Changes in 14-MeV Neutron Irradiate
