Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic martensitic steel for a high power spallation neutron source

被引:35
作者
Lee, EH [1 ]
Hunn, JD [1 ]
Rao, GR [1 ]
Klueh, RL [1 ]
Mansur, LK [1 ]
机构
[1] Oak Ridge Natl Lab, Div Met & Ceram, Oak Ridge, TN 37831 USA
关键词
D O I
10.1016/S0022-3115(98)00722-3
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To simulate radiation damage under a future Spallation Neutron Source (SNS) environment, irradiation experiments were conducted on a candidate 9Cr-2WVTa ferritic/martensitic steel using the Triple Ion Facility (TIF) at ORNL. Irradiation was conducted in single, dual and triple ion beam modes using 3.5 MeV Fe++, 360 keV He+, and 180 keV H+ at 80 degrees C, 200 degrees C and 350 degrees C. These irradiations produced various defects comprising black dots, dislocation loops, line dislocations, and gas bubbles, which led to hardening. The largest increase in hardness, over 63%, was observed after 50 dpa for triple beam irradiation conditions, revealing that both He and H are augmenting the hardening. Hardness increased less than 30%, after 30 dpa at 200 degrees C by triple beams, compatible with neutron irradiation data from previous work which showed about a 30% increase in yield strength after 27.2 dpa at 365 degrees C. However, the very large concentrations of gas bubbles in the matrix and on lath and grain boundaries after these simulated SNS irradiations make predictions of fracture behavior from fission reactor irradiations to spallation target conditions inadvisable. (C) 1999 Elsevier Science B.V. All rights reserved.
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页码:385 / 390
页数:6
相关论文
共 17 条
[1]  
BEMENT AL, 1970, P 2 INT C STRENGTH M, P693
[2]  
BROWN RD, 1987, ASTM STP, V956, P131
[3]  
CAMUS, 1997, P TMS S MAT SPALL NE
[4]   THE ROLE OF HELIUM IN THE DEVELOPMENT OF DAMAGE STRUCTURE AND SWELLING IN NEUTRON-IRRADIATED ALUMINUM [J].
FARRELL, K ;
CHICKERING, RW ;
MANSUR, LK .
PHILOSOPHICAL MAGAZINE A-PHYSICS OF CONDENSED MATTER STRUCTURE DEFECTS AND MECHANICAL PROPERTIES, 1986, 53 (01) :1-26
[5]   MODELING OF STRENGTHENING MECHANISMS IN IRRADIATED FUSION-REACTOR 1ST WALL ALLOYS [J].
GROSSBECK, ML ;
MAZIASZ, PJ ;
ROWCLIFFE, AF .
JOURNAL OF NUCLEAR MATERIALS, 1992, 191 :808-812
[6]  
JUNG P, IN PRESS FUSION TECH
[7]   THE MICROSTRUCTURE OF CHROMIUM-TUNGSTEN STEELS [J].
KLUEH, RL ;
MAZIASZ, PJ .
METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1989, 20 (03) :373-382
[8]   EMBRITTLEMENT OF 9CR-1MOVNB AND 12CR-1MOVW STEELS IRRADIATED IN HFIR [J].
KLUEH, RL ;
ALEXANDER, DJ .
JOURNAL OF NUCLEAR MATERIALS, 1992, 187 (01) :60-69
[9]  
KLUEH RL, 1997, ASTM STP, V1325
[10]   HARDNESS MEASUREMENTS OF AR+-BEAM TREATED POLYIMIDE BY DEPTH-SENSING ULTRA-LOW LOAD INDENTATION [J].
LEE, EH ;
LEE, Y ;
OLIVER, WC ;
MANSUR, LK .
JOURNAL OF MATERIALS RESEARCH, 1993, 8 (02) :377-387