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ASTM Selected Technical Papers
Influence of Radiation on Material Properties: 13th International Symposium (Part II)
By
FA Garner
FA Garner
1
Westinghouse Hanford Company
, P.O. Box 1970, W/A-58,
Richland, WA 99352
;
symposium chairman and editor
.
Search for other works by this author on:
CH Henager, Jr. Jr.
CH Henager, Jr. Jr.
2
Battelle Pacific Northwest Laboratory
, P.O. Box 999, 306/300,
Richland, WA 99352
;
symposium vice-chairman and editor
.
Search for other works by this author on:
N Igata
N Igata
3
University of Tokyo
,
7-3-1 Hongo, Bunkyo-ku, Tokyo 133,
Japan
;
symposium vice-chairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-0963-6
ISBN:
978-0-8031-0963-6
No. of Pages:
812
Publisher:
ASTM International
Publication date:
1987

Existing trend curves do not account for previous and more recently observed test and power reactor flux-level, thermal neutron and γ-ray field-induced effects. Any agreement between measured data and trend curve predictions that does not adequately represent the important neutron environmental and temperature effects as well as the microstructural damage processes, therefore, could be fortuitous. Empirically derived end-of-life (EOL) and life-extension-range (LER) trend curves are presented and discussed in this paper for high temperature [∼288°C (550°F)] irradiation of two weld, two plate, and two forging pressure vessel (PV) steels and low-temperature [∼60°C (140°F)] irradiation of one support structure-type steel.

Preliminary results of a comprehensive study of the effects of environmental variables (neutron spectrum, exposure, exposure rate, and the thermal and γ-ray fluxes associated with surveillance capsules and PV through-wall gradients) were used to develop these trend curves.

Pressurized water reactor (PWR) and boiling water reactor (BWR) plant-specific results together with those of the Poolside Facility (PSF) of the Oak Ridge Research Reactor (ORR) at the Oak Ridge National Laboratory (ORNL) and other research reactor experiments support the existence of a significant material-dependent flux-level effect for PV and support structure steels; that is, a steel may show a decrease, an increase, or no change in the measured Charpy shift with changes in fluxlevel. Further, the actual behavior of a material can change significantly as a function of neutron exposure; also, thermal neutron and γ-ray effects can contribute to observed changes in property, especially near steel-water interface positions with high thermal-to-fast-neutron ratios.

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,
P. N.
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Basis for Revision 2 of U.S. NRC Regulatory Guide 1.99
,”
Proceedings
,
10th MPA Seminar
,
Stuttgart, FRG
,
10
10
1984
.
2.
Perrin
,
J. S.
,
Wullaert
,
R. A.
,
Odette
,
G. R.
, and
Lombroso
,
M. P.
, “
Physically Based Regression Correlations of Embrittlement Data from Reactor PV Surveillance Programs
,” EPRI NP-3319,
Electric Power Research Institute
,
Palo Alto, CA
,
01
1984
.
3.
Guthrie
,
G. L.
, “
Charpy Trend Curves Based on 177 PWR Data Points
,”
LWR Pressure Vessel Dosimetry Improvement Program Quarterly Progress Report
, April 1983–June 1983, NUREG/CR-3391, Vol.
2
, HEDL-TME 83-22,
Nuclear Regulatory Commission
, Washington, DC,
04
1984
.
4.
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,
E. B.
, “
A Service Laboratory's View of the Status and Direction of Reactor Vessel Surveillance
,” in
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, ASTM STP 819,
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, Ed.,
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,
Philadelphia
,
1983
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Alberman
,
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,
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Nuclear Regulatory Commission
,
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Simons
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,”
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McElroy
,
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,
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,
Lippincott
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,
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,
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, and
Anderson
,
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, “
Trend Curve Data Development and Testing
,”
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, Oct. 1984–Sept. 1985, NUREG/CR-4307, Vol.
1
, HEDL-TME 85-14,
Nuclear Regulatory Commission
, Washington, DC, pp. HEDL-58-HEDL-74,
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10.
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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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, “
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,”
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, HEDL-TME 85-14,
Nuclear Regulatory Commission
, Washington, DC,
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, “
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Lucas
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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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,
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08
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15.
ASTM E706, “
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,”
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,
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,
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,
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Nuclear Regulatory Commission
,
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,
07
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, p. A. 1-4.
17.
ASTM E693, “
Standard Practice for Characterizing Neutron Exposures in Ferritic Steels in Terms of Displacements per Atom (dpa)
,”
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,
American Society for Testing and Materials
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18.
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,
G. L.
,
McElroy
,
W. N.
, and
Simons
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, “
Effect of Thermal Neutrons in Irradiation Embrittlement of PWR Pressure Vessel Plates and Welds
,”
LWR Pressure Vessel Surveillance Dosimetry Improvement Program Quarterly Progress Report
, April 1983–June 1983, NUREG/CR-3391, Vol.
2
, HEDL-TME 83-22,
Nuclear Regulatory Commission
, Washington, DC,
04
1984
.
19.
Gold
,
R.
,
Roberts
,
J. H.
, and
Doran
,
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, “
Determination of Gamma-Ray Displacement Rates
,”
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1
, HEDL-TME 85-14,
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.
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,
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3
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03
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.
21.
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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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,
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,
04
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.
22.
Hawthorne
,
J. R.
, and
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,
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, “
LWR Pressure Vessel Surveillance Dosimetry Improvement Program: Postirradiation Notch Ductility and Tensile Strength Determinations for PSF Simulated Surveillance and Through-Wall Specimen Capsules
,” NUREG/CR-3295, MEA-2017, Vol.
2
,
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,
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,
04
1984
.
23.
Stallmann
,
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, “
Statistical Evaluation of the Metallurgical Test Data in the ORR-PSF-PVS Irradiation Experiment
,” NUREG/CR-3815, ORNL/TM-9207,
Nuclear Regulatory Commission
,
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,
08
1984
.
24.
Perrin
,
J. S.
, “
Simulated Void Box Capsule (SVBC) Charpy Impact Test Results
,” EPRI NP-4630, NUREG/CR-3320, Vol.
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,
Electric Power Research Institute
,
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,
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.
25.
Guthrie
,
G. L.
,
McElroy
,
W. N.
, and
Anderson
,
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, “
A Preliminary Study of the Use of Fuel Management Techniques for Slowing Pressure Vessel Embrittlement
,”
Proceedings
,
4th ASTM-EURATOM Symposium on Reactor Dosimetry
,
Gaithersburg, MD
, March 22–26, 1982, NUREG/CP-0029,
Nuclear Regulatory Commission
,
Washington, DC
, Vol.
1
,
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, pp. 111-120.
26.
Guthrie
,
G. L.
,
McElroy
,
W. N.
, and
Anderson
,
S. L.
, “
Investigations of Effects of Reactor Core Loadings on PV Neutron Exposure
,”
LWR Pressure Vessel Surveillance Dosimetry Improvement Program: Quarterly Progress Report
, Oct.–Dec. 1981, NUREG/CR-2345, Vol.
4
, HEDL-TME 81-36,
Nuclear Regulatory Commission
, Washington, DC, Section E and Appendix,
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1982
.
27.
McElroy
,
W. N.
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,” HEDL-SA-2791 and
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,
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, pp. 184-227,
01
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.
28.
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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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, “
LWR Surveillance Dosimetry Improvement Program: PSF Metallurgical Blind Test Results
,”
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,
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,
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, NUREG/CP-0057,
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,
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,
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29.
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,
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1983
.
30.
Davies
,
L. M.
 et al
, “
Analysis of the Behavior of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation—The UK Programme
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,
Harwell, UK
,
04
1983
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31.
Davis
,
L. M.
and
Squires
,
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Williams
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 et al
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The Influence of Copper, Nickel, and Irradiation Temperature on the Irradiation Shift of Low Alloy Steels
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,
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, Sept. 12–14 1985.
33.
Stahlkopf
,
K. E.
and
Marston
,
T. U.
, “
A Comprehensive Approach to Radiation Embrittlement Analysis
,”
Proceedings
,
IAEA Specialists' Meeting on Irradiation Embrittlement, Thermal Annealing and Surveillance of Reactor Pressure Vessels
,
Vienna, Austria
, Feb. 26–March 1, 1979, IWG-RRPC-79/2,
International Atomic Energy Agency
,
Vienna, Austria
,
12
1979
.
34.
Steele
,
L. E.
, Ed., in
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, ASTM STP 819,
American Society for Testing and Materials
,
Philadelphia, PA
,
11
1983
.
35.
Steele
,
L. E.
,
Davis
,
L. M.
,
Ingham
,
T.
, and
Brumovsky
,
M.
, “
Results of IAEA-Coordinated Research Programs on Irradiation Effects on Advanced Pressure Vessel Steels
,”
Proceedings
,
12th Conference on Effects of Radiation on Materials
, ASTM STP 870,
Williamsburg, VA
,
06
1984
.
36.
Pachur
,
D.
and
Sievers
,
G.
, “
Development Programs on Irradiation Embrittlement of Low Alloy Pressure Vessel Steels in the Federal Republic of Germany
,” in
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, ASTM STP 570,
American Society for Testing and Materials
,
Philadelphia, PA
, pp. 555-564,
1975
.
37.
Pachur
,
D.
, “
Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels
,” in
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, ASTM STP 725,
American Society for Testing and Materials
,
Philadelphia, PA
, pp. 5-19,
1981
.
38.
Pachur
,
D.
, “
Mechanical Properties of Neutron-Irradiated Reactor Pressure Vessel Steel Dependent on Radiation Mechanisms,” from the ANS Special Session on Correlations and Implications of Neutron Irradiation Embrittlement of Pressure Vessel Steels
,” Detroit, MI, June 12–16, 1983,
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39.
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,
J. R.
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, ASTM DS54,
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,
Philadelphia, PA
,
1974
.
40.
Serpan
,
C. Z.
, Jr.
, and
Hawthorne
,
J. R.
, “
Through-Thickness Notch Ductility and Tension Properties as a Function of Neutron Exposure to a Simulated Pressure Vessel Wall of A302-B Steel
,”
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41.
Serpan
,
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, Jr.
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,”
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, pp. 108-118,
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42.
Simons
,
R. L.
, “
Re-evaluation of Ferritic Steel ΔDBTT Data Used in Damage Function Analysis
,”
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,
R. L.
, “
Re-evaluation of Dosimetry for Test Reactor Irradiations Used to Obtain ΔNDTT Data for Pressure Vessel Steels
,”
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, Oct.–Dec. 1982, NUREG/CR-2805, Vol.
4
, HEDL-TME 82-21,
Nuclear Regulatory Commission
, Washington, DC, pp. HEDL-14-HEDL-22,
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44.
Steele
,
L. E.
, Ed., in
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, ASTM STP 784,
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,
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,
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45.
McElroy
,
W. N.
, Ed., “
LWR Pressure Vessel Surveillance Dosimetry Improvement Program: LWR Power Reactor Surveillance Physics-Dosimetry Data Base Compendium
,” NUREG/CR-3319, HEDL-TME 85-3,
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, Jr.
, and
McElroy
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W. N.
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Wullaert
,
R. A.
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Spelzman
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,
Berggren
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R. G.
, and
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, Jr.
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,” NUREG/CR-4092, ORNL/TM-9491,
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52.
Maricchiolo
,
C.
,
Milella
,
P. P.
, and
Pini
,
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, “
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,”
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Brilland
,
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,
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,
F.
, and
Houssin
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,”
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,
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,
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