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ASTM Selected Technical Papers
Effects of Radiation on Materials
By
D Kramer
D Kramer
1
Rockwell International
,
Canoga Park, Calif. 91304
;
symposium chairman and co-editor
.
Search for other works by this author on:
HR Brager
HR Brager
2
Westinghouse Hanford Co.
,
editor
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JS Perrin
JS Perrin
3
Batelle Columbus Laboratories
,
editor
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ISBN-10:
0-8031-0755-2
ISBN:
978-0-8031-0755-7
No. of Pages:
777
Publisher:
ASTM International
Publication date:
1981

Nickel-manganese-molybdenum low-alloy steels are employed today for the beltline regions of French pressurized water reactor vessels subject to radiation embrittlement. Brittle ductile transition temperature shifts observed in Charpy V-notch tests were used to evaluate the effects of some elements on embrittlement. The role of residuals such as phosphorus, copper, and tin was carefully studied with special laboratory heats. The detrimental effects of phosphorus and copper were quantitatively determined, particularly for low copper content heats. Tin also appears to be undesirable. Silicon and nickel contents may be modified in the future. Their effects were examined. It was not possible to establish the role played by silicon. The detrimental effects of nickel additions were, however, clearly demonstrated. The effects of certain other oligoelements were also studied.

1.
Hawthorne
,
J. R.
,
Journal of Testing and Evaluation
 0090-3973, Vol.
1
, No.
5
,
09
1973
, pp. 439-444.
2.
Petrequin
,
P.
and
Soulat
,
P.
in
Reliability Problem of Reactor Pressure Components
,
International Atomic Energy Agency
, Vol.
1
,
Vienna
,
1978
, pp. 347-378.
3.
Les Irradiations en Pile
,”
Bulletin d'Informations Scientifiques et Techniques
,
Commissariat à l'Energie Atomique
,
France.
, Nos.
153/154
Nov.–Dec. 1970, pp. 15, 91.
4.
Mynatt
,
F. R.
,
Engle
,
W. W.
,
Grispzner
,
M. L.
,
Rhoades
,
W. A.
, and
Rodgers
,
R. T.
,
DOT III, Two Dimensional Discrete Ordinates Transport Code
,” CCC 209, ORNL TM 4280,
Oak Ridge National Laboratory
,
Oak Ridge, Tenn.
,
06
1973
.
5.
Schett
,
A.
,
Okamoto
,
K.
,
Lesca
,
L.
,
Fröhner
,
F. H.
,
Liskien
,
H.
, and
Paulsen
,
A.
, “
Compilation of Threshold Reaction Neutron Cross-Sections for Neutron Dosimetry and Other Applications
,”
European American Data Committee 95 “U” Neutron Data Compilation Center
,
02
1974
.
6.
Calamand
,
A.
, “
Cross-Sections for Fission Neutron Spectrum Induced Reactions
,”
International Atomic Energy Agency Technical
Reports Series No. 156, Vienna,
1974
.
7.
Lott
,
M.
,
Genthon
,
J. P.
,
Gervaise
,
F.
,
Mas
,
P.
,
Mougnot
,
J. C.
, and
Van Doan
,
Nguyen
, “
Sections Efficaces de Créations de Dommages
,”
International Atomic Energy Agency
, SM-170/65,
Vienna
,
05
1973
.
8.
Oldfield
,
W.
,
Standardization News
, Vol.
3
, No.
11
,
1975
, pp. 24.
9.
Effect of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials
,”
Nuclear Regulatory Agency Regulatory Guide 1.99
, Revision 1,
04
1977
.
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