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ASTM Selected Technical Papers
Effects of Radiation on Materials: 21st International Symposium
By
ML Grossbeck
ML Grossbeck
1
University of Tennessee
,
Knoxville, Tennessee Symposium Chair and Editor
Search for other works by this author on:
TR Allen
TR Allen
2
University of Wisconsin
?
Madison, Wisconsin Symposium Co-Chair and Editor
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RG Lott
RG Lott
3
Westinghouse Electirc Company
?
Pittsburgh, Pennsylvania Symposium Co-Chair and Editor
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AS Kumar
AS Kumar
4
University of Missouri Rolla
?
Rolla, Missouri Symposium Co-Chair and Editor
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ISBN-10:
0-8031-3477-0
ISBN:
978-0-8031-3477-5
No. of Pages:
758
Publisher:
ASTM International
Publication date:
2004

Mechanical properties after neutron irradiation of V-4Cr-4Ti-0.1Si-0.1Al-0.1Y and V-4Cr-4Ti-0.1Si-0.1Al-0.3Y alloys (nominal weight percentage) were studied. Neutron irradiation was carried out at 290°C to 8×1022 n/m2 (E>1 MeV, about 0.014 dpa) in the Japan Materials Testing Reactor (JMTR). Tensile tests were carried out using miniaturized specimens at ambient temperature and irradiation temperature. Charpy impact tests were conducted at temperatures from -196 to 0°C using an instrumented machine. There is little difference in tensile properties after neutron irradiation between the two alloys. Increase in yield stress was relatively small (∼100 MPa), and uniform elongation remained more than 10%. Because of a low concentration of interstitial impurities, good tensile properties could be retained even after neutron irradiation at 290°C. Ductile-to-brittle transition temperature (DBTT) of V-4Cr-4Ti-0.1Si-0.1Al-0.1Y alloys hardly changed, whereas absorbed energy was slightly reduced after neutron irradiation.

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, to be published
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