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ASTM Selected Technical Papers
Effects of Radiation on Materials: 22nd Symposium
By
TR Allen
TR Allen
1
Symposium Chair and Editor
?
University of Wisconsin
?
Madison, Wisconsin
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RG Lott
RG Lott
2
Symposium Co-Chair and Editor
?
Westinghouse Electric Company
?
Pittsburgh, Pennsylvania
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JT Busby
JT Busby
3
Symposium Co-Chair and Editor
?
Oak Ridge National Laboratory
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AS Kumar
AS Kumar
4
Symposium Co-Chair and Editor
?
University of Missouri-Rolla
?
Rolla, Missouri
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ISBN-10:
0-8031-3401-0
ISBN:
978-0-8031-3401-0
No. of Pages:
406
Publisher:
ASTM International
Publication date:
2006

Surveillance materials consisting of a SA-508 Class 2 forging, a Mn-Mc-Ni Linde 80 submerged-arc weld, and an SA-533, Grade B, Class 1, correlation monitor material were thermally aged on a commercial reactor pressure vessel. The materials were exposed to a thermal environment of 282°C for 209 000 h. This temperature is below the range (minimum of 370°C) where the effects of long-term thermal aging are typically considered relevant. Charpy impact, master curve transition temperature, upper-shelf fracture toughness, and tensile testing were conducted to evaluate the long-term thermal aging changes in material properties. Small changes in the impact properties were observed for all the materials, but were generally within the 95 % confidence bounds for typical Charpy data. Upper-shelf energy also showed small variations, but a general decrease for all materials was not seen. Fracture toughness testing at the upper shelf indicated that the upper-shelf toughness had increased, however the data is scattered. Master curve T0 testing in the transition region showed little change in the forging and plate results; however an improvement in the transition temperature of the weld metal was measured.

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,
EPRI
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,
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,
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,
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, ,
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,
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,”
Effects of Radiation on Materials, Vol. 17, ASTM STP 1270
,
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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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,”
Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175
,
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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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4.
Materials Reliability Program: Validation and Use of ASTM E 900-02 for Reactor Pressure Vessel Integrity (MRP-86)
,
EPRI
,
Palo Alto, CA
,
2003
.
5.
Pareige
,
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,
Russell
,
K. F.
,
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,
R. E.
, and
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,
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Influence of Long-Term Thermal Aging on the Microstructural Evolution of Nuclear Reactor Pressure Vessel Materials: An Atom Probe Study
,”
J. Nucl. Mater.
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250
,
1997
, pp. 176–183.
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