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ASTM Selected Technical Papers
Effects of Radiation on Materials: 18th International Symposium
By
RK Nanstad
RK Nanstad
1
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
Symposium Chair and Editor
Search for other works by this author on:
ML Hamilton
ML Hamilton
2
Pacific Northwest National Laboratory
,
Richland, Washington
;
Symposium Co-Chair and Editor
Search for other works by this author on:
FA Garner
FA Garner
3
Pacific Northwest National Laboratory
,
Richland, Washington
;
Symposium Co-Chair and Editor
Search for other works by this author on:
AE Kumar
AE Kumar
4
University of Missouri-Rolla
,
Rolla, Missouri
;
Symposium Co-Chair and Editor
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ISBN-10:
0-8031-2614-X
ISBN:
978-0-8031-2614-5
No. of Pages:
1162
Publisher:
ASTM International
Publication date:
1999

A series of six austenitic stainless steels and two ferritic alloys were irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He transmutation rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor. After an atomic displacement level of 7.4 dpa was achieved, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation temperatures of 60, 200, 330, and 400°C were studied with internally pressurized tubes of type 316 stainless steel, PCA, HT 9, and a series of four laboratory heats of: Fe-13.5Cr-15Ni, Fe-13.5Cr-35Ni, Fe-13.5Cr-15Ni- 0.18Ti, and Fe-16Cr. At 330°C, irradiation creep was shown to be linear with fluence and stress. There was little or no effect of cold-work on creep under these conditions at all temperatures investigated. The HT9 demonstrated a large deviation from linearity at high stress levels, and a minimum in irradiation creep with increasing stress was observed in the Fe-Cr-Ni ternary alloys.

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