Evaluation of the BR3 third core vessel steel specimens

Research output: Report/bookBLG - Open reportpeer-review

Institutes & Expert groups

  • KUL - Katholieke Universiteit Leuven
  • Verenigde Energiebedrijven van het Scheldeland N.V.

Documents & links


  • BLG-459

    Final published version, 7.73 MB, PDF document


Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 1020 nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.


Original languageEnglish
PublisherSCK CEN
Number of pages22
Publication statusPublished - Jul 1971

Publication series

NameSCK CEN Reports
PublisherSCK CEN

ID: 7845577