Thermal embrittlement of reactor vessel steels

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Description

As a result of observations of possible thermal embrittlement from recent studies with welds removed from retired steam generators of the Palisades Nuclear Plant (PNP), an assessment was made of thermal aging of reactor pressure vessel (RPV) steels under nominal reactor operating conditions. Discussions are presented on (1) data from the literature regarding relatively low-temperature thermal embrittlement of RPV steels; (2)relevant data from the US power reactor-embrittlement data base (PR-EDB); and (3)potential mechanisms of thermal embrittlement in low-alloy steels.

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6 p.

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Corwin, W. R.; Nanstad, R. K.; Alexander, D. J.; Stoller, R. E.; Wang, J. A. & Odette, G. R. June 1, 1995.

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Description

As a result of observations of possible thermal embrittlement from recent studies with welds removed from retired steam generators of the Palisades Nuclear Plant (PNP), an assessment was made of thermal aging of reactor pressure vessel (RPV) steels under nominal reactor operating conditions. Discussions are presented on (1) data from the literature regarding relatively low-temperature thermal embrittlement of RPV steels; (2)relevant data from the US power reactor-embrittlement data base (PR-EDB); and (3)potential mechanisms of thermal embrittlement in low-alloy steels.

Physical Description

6 p.

Notes

INIS; OSTI as DE95012298

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  • 13. international conference on structural mechanics in reactor technology (SMiRT-13), Porto Alegre (Brazil), 13-18 Aug 1995

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  • Other: DE95012298
  • Report No.: CONF-950804--3
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 69435
  • Archival Resource Key: ark:/67531/metadc706620

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • June 1, 1995

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • Oct. 3, 2017, 4:29 p.m.

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Corwin, W. R.; Nanstad, R. K.; Alexander, D. J.; Stoller, R. E.; Wang, J. A. & Odette, G. R. Thermal embrittlement of reactor vessel steels, article, June 1, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc706620/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.