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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 subject of this research concerns a vast irradiation program of the stainless steel material that is used extensively in Liquid Metal Fast Breeder Reactors (LMFBRs) irremoveable primary circuit components. Irradiations covering the 0.1, 0.3, 1, and 2 displacements per atom (dpa) neutron damage have been planned. The results presented concern the nought, 0.1, 0.3, and 1 dpa irradiations. Irradiation and tests are conducted at 350°C and 550°C on plane-sided three-point bend bars. The Type 316H stainless steel has been considered in the base condition, the welded deposits, and the heat-affected zone (HAZ) material. To study the stable crack extension with rising loads behavior of this steel, crack-growth resistance curves have been elaborated using key curves. Consistent crack-growth resistance curves are obtained in all cases. The results indicate a low degradation with increasing fluence for the weld material at both temperatures. The base material has given indications of strongly decreasing toughness at 0.1 dpa and at the 1 dpa fluences at 550°C with respect to the results at 0 and 0.3 dpa. No significant alterations have been found at 35O°C and at all fluences. The HAZ material was studied too, and it was found that all J values corresponding to various crack advances fell within the base material results at 350°C as upper bound and the weld material at 55O°C as lower bound at corresponding fluence levels.

1.
Bernard
,
J.
and
Verzeletti
,
G.
, “
Elasto-PIastic Fracture Toughness Characteristics of Irradiated 316 Grade Stainless Steel
,” presented at the
Symposium on User's Experience with Elastic-Plastic Fracture Toughness Test Methods
, 20-22 April
1983
,
Louisville, KY
.
2.
Hutchinson
,
J. N.
and
Paris
,
P. C.
in
Elastic-Plastic Fracture, ASTM STP 668
,
Landes
J. D.
,
Begley
J. A.
, and
Clarke
G. A.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1979
, pp. 37–64.
3.
Ernst
,
H. A.
and
Paris
,
P. C.
, “
Technique of Analysis of Load-Displacement Records by J-Integral Methods
,” U. S. Nuclear Regulatory Commission Report, NUREG/CR-122, Jan.
1980
.
4.
Ernst
,
H. A.
in
Elasto-Plastic Fracture: Second Symposium ASTM STP 803
,
Shih
C. F.
and
Gudas
J. P.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1983
, pp. I–191-I-213.
5.
Turner
,
E. C.
in
Advances in Elasto-Plastic Fracture Mechanics
,
Larsson
L. H.
, Ed.,
Applied Science Publishers Ltd.
,
1980
, pp. 139–164.
6.
Paris
,
P.
and
Johnson
,
R.
, “
A Method of Application of Elastic-Plastic Fracture Mechanics to Nuclear Vessel Analysis
,” Seminar on EPFM, sponsored by
Fraunhofer Institut für Werstoffmechanik
,
Freiburg, Germany
, June
1981
.
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