SYMPOSIA PAPER Published: 01 January 2006

Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209000 H at 282 °C


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.

Author Information

Gunawardane, HP
Materials and Structural Analysis, AREVA, Lynchburg, VA
Hall, BJ
Materials and Structural Analysis, AREVA, Lynchburg, VA
Rosinski, ST
EPRI, Charlotte, NC
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Developed by Committee: E10
Pages: 236–244
DOI: 10.1520/STP37581S
ISBN-EB: 978-0-8031-5518-3
ISBN-13: 978-0-8031-3401-0