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ASTM Selected Technical Papers
Effects of Radiation on Materials: Sixteenth International Symposium
By
AE Kumar
AE Kumar
1
University of Missouri-Rolla
,
Rolla, MO
;
symposium chairman and editor
.
Search for other works by this author on:
DS Gelles
DS Gelles
2
Battelle Pacific Northwest Laboratory
,
Richland, WA
;
symposium cochairman and editor
.
Search for other works by this author on:
RK Nanstad
RK Nanstad
3
Oak Ridge National Laboratory
,
Oak Ridge, TN
;
symposium cochairman and editor
.
Search for other works by this author on:
TA Little
TA Little
4
Harwell Laboratory
,
Oxfordshire,
UK
;
symposium cochairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-1488-5
ISBN:
978-0-8031-1488-3
No. of Pages:
1344
Publisher:
ASTM International
Publication date:
1994

The embrittlement of microalloyed and grain-refined high tensile strength steel plates, which are to be extensively used as structural components in nuclear reactors in India, was studied after irradiating to neutron fluences between 1.7 x 1017 and 1.0 x 1019 n.cm2 (E > 1 MeV). The irradiations were carried out at less than 150°C. The results of room temperature tension tests and the instrumented impact tests over a range of temperature are presented. Irradiation stability of the steel is monitored by measuring the increase in yield strength and the elevation in the ductile-brittle-transition temperature after neutron irradiation. Attempts have been made to assess the extent of embrittlement as a function of neutron exposure. The results have been compared with both vintage and advanced pressure vessel steels.

1.
Steele
,
L. E.
, “
Neutron Irradiation Embrittlement of Pressure Vessel Steels
,”
Atomic Energy Review
, Vol.
7
, No.
2
,
1969
, pp. 3–133.
2.
Ganguly
,
C.
,
Anantharaman
,
S.
, and
Sivaramakrishnan
,
K. S.
, “
Effect of Neutron Irradiation on the Mechanical Properties of Microalloyed Steel for Reinforced Cement Concrete
,” in
Effects of Radiation on Materials: 15th International Symposium
, ASTM STP 1125,
American Society for Testing and Materials
,
Philadelphia
,
1992
, pp. 1304–1310.
3.
Druce
,
S. G.
and
Edwards
,
B. C.
, “
Development of PWR Pressure Vessel Steels
,”
Nuclear Energy
, Vol.
19
, No.
5
,
10
1980
, pp. 347–360.
4.
Server
,
W. I.
, “
General Yielding of Charpy V-Notch and Pre-Cracked Charpy Specimens
,”
Journal of Engineering Materials and Technology
, Vol.
100
,
1978
, pp. 183–188.
5.
Sivaramakrishnan
,
K. S.
,
Chatterjee
,
S.
,
Anantharaman
,
S.
,
Balakrishnan
,
K. S.
,
Viswanathan
,
U. K.
, and
Roy
,
P. R.
, “
BWR Pressure Vessel Surveillance Programme
,” in
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume)
ASTM STP 909,
American Society for Testing and Materials
,
Philadelphia
,
1986
, pp. 106–117.
6.
Sivaramakrishnan
,
K. S.
,
Chatterjee
,
S.
,
Anantharaman
,
S.
,
Balakrishnan
,
K. S.
, and
Viswanathan
,
U. K.
, “
Irradiation Embrittlement of Reactor Pressure Vessel Steels
,”
Head, Library and Information Division, Bhabra Atomic Research Centre
,
Bombay 400 085, India
, BARC-1237,
1984
.
7.
Nanstad
,
R. K.
,
Iskander
,
S. K.
,
Rowcliffe
,
A. F.
,
Corwin
,
W. R.
, and
Odette
,
G. R.
, “
Effects of 50°C Surveillance and Test Reactor Irradiations on Ferritic Pressure Vessel Steel Embrittlement
,” in
Effects of Radiation on Materials: 14th International Symposium (Vol. II)
, ASTM STP 1046,
American Society for Testing and Materials
,
Philadelphia
,
1990
, pp. 5–29.
8.
Miannay
,
D.
,
Dussarte
,
D.
, and
Soulat
,
P.
, “
The Nil-Ductility Temperature Shift Arising from Irradiation as Predicted Through the French Test Reactor Experiments
,” in
Effects of Radiation on Materials
, ASTM STP 1046,
American Society for Testing and Materials
,
Philadelphia
,
1990
, pp. 284–304.
9.
Nichols
,
F. A.
, “
Theory of Radiation Embrittlement and Recovery of Radiation Damage in Ferritic Steels
,”
Philosophical Magazine
 1478-6435, Vol.
14
, No.
128
,
1966
, pp. 335–342.
10.
Odette
,
G. R.
,
Lombozoa
,
P. M.
, and
Wullaert
,
R. A.
, “
Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel Steels
,” in
Effects of Radiation on Materials
, ASTM STP 870,
American Society for Testing and Materials
,
Philadelphia
,
1985
, pp. 840–860.
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