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ASTM Selected Technical Papers
Effects of Radiation on Materials: 12th International Symposium Volume II
By
F. A. Garner
F. A. Garner
STP Editor
1
Westinghouse Hanford Co.
,
Richland, WA 99352,
US
.
Search for other works by this author on:
J. S. Perrin
J. S. Perrin
STP Editor
2
Office of Nuclear Waste Isolation
,
Columbus, OH 43201,
US
Search for other works by this author on:
ISBN:
978-0-8031-0592-8
No. of Pages:
745
Publisher:
ASTM International
Published online:
2018
Published in print:
1985

The capabilities of the Materials Open Test Assembly (MOTA) irradiation vehicle and the Fast Flux Test Facility (FFTF) cover gas monitoring system are described in relation to the creep rupture experiment during FFTF Cycle 2 operation. The creep rupture specimen matrix in MOTA includes both U. S. and foreign alloys at irradiation temperatures of 575, 605, 670, and 750°C. For exposure times less than 2400 h and fluences less than 3.2 × 1022 neutrons (n)/cm2 (E > 0.1 MeV), neutron irradiation does not impact the rupture times for the U. S. alloys irradiated in MOTA.

1.
Fish
,
R. L.
, “
Creep Rupture Properties of 20% Cold Worked Type 316 Stainless Steel After High Fluence Neutron Irradiation
,”
Nuclear Technology
, Vol.
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, Aug.
1977
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2.
Gilbert
,
E. R.
and
Chin
,
B. A.
,
Nuclear Technology
, Vol.
52
, Feb.
1981
, pp. 273–283.
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Lovell
,
A. J.
,
Chin
,
B. A.
, and
Gilbert
,
E. R.
, “
In-Reactor Creep Rupture of 20% CW AISI 316 Stainless Steel
,”
Journal of Nuclear Materials
, Vol.
16
,
1981
.
4.
Puigh
,
R. J.
,
Lovell
,
A. J.
, and
Garner
,
F. A.
, “
Thermal Creep and Stress-Affected Precipitation of 20% Cold Worked 316 Stainless Steel
,” to be published in the
Journal of Nuclear Materials
as part of the Proceedings for the Third Topical Meeting on Fusion Reactor Materials,
Albuquerque, NM
, Sept.
1983
.
5.
Bauer
,
R. E.
and
Truitt
,
R. W.
, “
Materials Open Test Assembly (MOTA) Irradiation in FFTF
,” presented at
Twelfth International Symposium on the Effects of Radiation on Materials
,
American Society for Testing and Materials
,
Williamsburg, VA
, 18-20 June
1984
.
6.
Gilbert
,
E. R.
and
Chin
,
B. A.
in
Effects of Radiation of Materials: Tenth Conference, ASTM STP 725
,
Kramer
D.
,
Brager
H. R.
, and
Perrin
J. S.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1981
, pp. 665–679.
7.
Figg
,
J. A.
,
McCormick
,
N. J.
,
Schenter
,
R. E.
, and
Schmittroth
,
F.
, “
Gas Tag Identification of Failed Reactor Assemblies-IV. Analysis Methods
,”
Nuclear Technology
, Vol.
50
, Aug.
1980
.
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