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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
Publication date:
1985

Based on a large body of test and power reactor data, empirical relationships between irradiation strengthening and embrittlement are derived. It is shown that the Charpy V-notch (Cv) 41-J indexed transition temperature increases and the upper-shelf energy decreases systematically with increases in the yield stress. The transition temperature shifts are related to two mechanisms: (1) increases in the maximum temperature of elastic-cleavage fracture, and (2) decreases in the slope of the Cv energy versus test temperature curve associated with reductions in the upper-shelf energy. The cleavage shift contribution, which is usually dominant, can be predicted from the initial temperature of fracture at general yield and the change in ambient temperature static yield stress. In developing this simplified cleavage fracture model, it is shown that: (a) yield stress changes are independent of temperature and strain rate; (b) the increase in yield stress with decreasing temperature is independent of the strain rate, irradiation, and metallurgical state; and (c) the microcleavage fracture stress is independent of irradiation and temperature. A semi-empirical procedure for estimating the shift contribution due to upper-shelf energy decreases and the total temperature shift at 41 J, based on the observation of an approximately constant temperature interval of the transition regime, is proposed, along with a method for forecasting the entire irradiated Cv curve.

1.
Odette
,
G. R.
and
Lombrozo
,
P. M.
, “
Physically-Based Regression Correlations of Embrittlement Data from Reactor Pressure Vessel Surveillance Programs
,” EPRI NP-3319,
Electric Power Research Institute
,
1984
.
2.
Varsik
,
J. D.
, “
Evaluation of the Irradiation Response of Reactor Pressure Vessel Materials
,” EPRI NP-2720,
Electric Power Research Institute
,
1982
.
3.
Guthrie
,
G. L.
,
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,
American Nuclear Society
, Vol.
44
,
1983
, p. 223.
4.
Oldfield
,
W.
,
McConnell
,
P.
,
Server
,
W.
, and
Oldfield
,
F.
, “
Irradiated Pressure Vessel Steel Data Base
,” EPRI NP-2428,
Electric Power Research Institute
,
1982
.
5.
Yanichko
,
S. E.
,
Anderson
,
S. L.
,
Shogun
,
R. P.
, and
Lott
,
R. G.
,
Topical Reports on the Power Reactor Surveillance Capsules: R. E. Ginna, Cap T (April 1982, WCAP-10086); S. A. Jose Cabrera, Cap N (Oct. 1982, WCAP 10185); Connecticut Yankee, Cap D (Jan. 1983, WCAP-10236); H. B. Robinson-2, Cap T (March 1983, WCAP-10304)
. These were issued as part of the EPRI-sponsored Steady-State-Embrittlement Program, RP 1 21-3, T. U. Marston, project manager,
Westinghouse Electric Corporation, Nuclear Technology Division
; T. R. Mager, principal investigator.
6.
Pachur
,
D.
and
Sievers
,
G.
, “
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,”
KFA
Jülich, April
1974
.
7.
Hawthorne
,
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,
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,
Loss
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,
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,
H. E.
,
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,
A. L.
, and
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, “
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,” EPRI NP-2782,
Electric Power Research Institute
,
1982
.
8.
Anderson
,
S. L.
,
DeFlitch
,
C.
,
Jouris
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,
Lott
,
R. G.
,
Mager
,
T. R.
,
Mancuso
,
J. F.
,
Meyer
,
T. A.
,
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,
R. D.
,
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,
J. S.
,
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,
R. P.
,
Spitznagel
,
J. A.
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Yanichko
,
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Feasibility of and Methodology for Thermal Annealing an Embrittled Reactor Vessel
,” Vol.
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, EPRI NP-2712,
Electric Power Research Institute
,
1982
.
9.
Buswell
,
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, “
A Comparison of Reactor Surveillance and Materials Test Reactor Data on Radiation Embrittlement of Water Reactor Pressure Vessel Steels
,”
British Central Electricity Generating Board
, CEGB-TPRD/B/0351/N83,
1983
.
10.
Hawthorne
,
J. R.
,
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,
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, and
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, “
Light Water Reactor Pressure Vessel Dosimetry Program. Post-Irradiation Notch Ductility and Tensile Strength Determinations for the PSF Simulated Pressure Vessel Through-Wall Specimen Capsules
,” NUREG/CR-3457,
Nuclear Regulatory Commission
,
1984
.
11.
Stelzman
,
W. J.
and
Berggren
,
R. G.
, “
Radiation Strengthening and Embrittlement in Heavy-Section Plates and Welds
,” ORNL-4871,
Oak Ridge National Laboratory
, Oak Ridge, TN,
1973
.
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Hawthorne
,
J. R.
,
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, Vol.
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,
1971
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13.
Fohl
,
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,
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,
C.
, and
Anders
,
D.
,
Effects of Irradiation on Materials— llth International Symposium, ASTM STP 782
,
Brager
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and
Perrin
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, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1982
, p. 520.
14.
Davies
,
L. M.
,
Ingham
,
T.
, and
Squires
,
R. L.
,
Effects of Irradiation on Materials— llth International Symposium, ASTM STP 782
,
Brager
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and
Perrin
J. S.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1982
, p. 433.
15.
Hawthorne
,
J. R.
,
Radiation Effects Information Generated on the ASTM Reference Correlation—Monitor Steels ASTM DS-54
,
American Society for Testing and Materials
,
Philadelphia
,
1971
.
16.
Galliani
,
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,
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,
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,
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,
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,
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, and
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,
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Italian Commission for Electric Energy, Division of Production and Transmission, Nuclear Section
,
1979
.
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,
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, and
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,
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, Vol.
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, No.
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,
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19.
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,
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,
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, Vol.
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, No.
11
,
1975
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20.
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,
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,
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,
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, Vol.
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,
1968
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21.
Tetelman
,
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,
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,
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, and
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,
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, Vol.
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,
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22.
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,
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in
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,
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,
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,
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, p. 148.
23.
Knott
,
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in
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, Vol.
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,
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,
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,
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24.
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,
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,
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,
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25.
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,
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,
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, and
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,
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,
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, Vol.
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,
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26.
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,
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27.
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,
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,
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28.
Beremin
,
F. M.
,
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, Vol.
14
,
1983
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29.
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,
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30.
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,
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31.
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,
J. M.
and
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,
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, Vol.
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,
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, p. 303.
32.
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,
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,
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,
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, and
Wullaert
,
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,
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, Vol.
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,
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, p. 1557.
33.
Yanichko
,
S. E.
,
Anderson
,
S. L.
,
Shogun
,
R. P.
, and
Lott
,
R. G.
,
Topical Reports on the Power Reactor Surveillance Capsules: Zion 1, Cap U (March 1981, WCAP-9890); Dresden-3, Cap 4 (Jan. 1982 -WCAP, 10030); Maine Yankee Acc. Cap 2 (March 1981, WCAP-9875); Quad Cities, Cap 3 (August 1981, WCAP-9920); Quad Cities 2 (April 1982, WCAP-10064); Kewanee, Cap R (March 1981, WCAP 9878) Point Beach 2, Cap R (Dec. 1979, WCAP 9635)
. These were issued as part of the EPRI-sponsored Steady-State Embrittlement Program, PR 1021-3, T. U. Marston, project manager; by
Westinghouse Electric Corporation, Nuclear Technology Division
, T. R. Mager, principal investigator.
34.
Analysis of Radiation Embrittlement Reference Toughness Curves
,”
Wullaert
R. A.
, Ed., EPRI Semiannual Progress Reports 5 and 6, RP-886-1, FCC 79-5,
Fracture Control Corporation
, Goleta, CA,
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.
35.
Wullaert
,
R. A.
,
Sheckherd
,
J. W.
, and
Smith
,
R. W.
in
Irradiation Effects on the Microstructure and Properties of Metals, ASTM STP 611
,
Shober
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, Ed.,
American Society for Testing and Materials
,
Philadelphia
,
1976
, p. 400.
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