The BR3 pressure vessel irradiation surveillance program evaluation of the first and second core vessel steel specimens

P. De Meester, M. Potemans

Research outputpeer-review

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Abstract

First and second core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 ft-lb. for samples being irradiated for an integrated dose of 5.5 x 1018 , 1.2 x 1019, 9.5 x 1019, 2.2 x 1020 n.v.t. is resp. +30, +50, +140 and +200*C. Considering the sample positions, it can be concluded that the BR3 vessel is still safe. I f, in the future, a drastic change would be observed, annealing of the vessel could be considered.
Original languageEnglish
PublisherSCK CEN
Number of pages15
StatePublished - Apr 1966
Externally publishedYes

Publication series

NameSCK CEN Reports
PublisherSCK CEN
No.BLG-372

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