Fracture Toughness of the Ni-Modified A302-B plate of the BR3 Reactor Pressure Vessel.

Research output: Contribution to journalArticlepeer-review

Documents & links



The present paper aims to compare regulatory predictions of fracture toughness to direct measurements using precracked Charpy specimens tested in three-point bending. Trepans were extracted from the vessel of the BR3 reactor in order to perform fracture toughness tests in addition to charpy impact and tensile testing. This vessel was successfully wet-annealed at 343°C during 1 week after a maximum neutron fluence of 3.3 10E19 n/cm². The reactor is presently under decommissioning after a maximum neutron fluence of 4.0 10 E19 n/cm². The trepans (base metal and weld) were taken from tworegions: vessel mid-plane and nozzle elevation (no neutrons, negligible thermal aging). Here, the base metal (Ni-modified A-302 grade B) is investigated: Tensile, Charpy impact and fracture toughness tests were performed at thickness ranging from 1/4T to 1/2T.


Original languageEnglish
Number of pages162
JournalJournal of ASTM International: Selected technical papers
Publication statusPublished - 2000


  • Fracture toughness, Charpy impact, tensile, transition, irradiation, Ni-modified A-302 grade B reactor pressure vessel steel, reference temperature

ID: 3450672