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

Rachid Chaouadi; Albert Fabry; Eric van Walle; José Van de Velde

doi:10.1520/stp12389s

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

Rachid Chaouadi, Albert Fabry, Eric van Walle, José Van de Velde

Research output › peer-review

Abstract

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 language	English
Number of pages	162
Journal	Journal of ASTM International: Selected technical papers
DOIs	https://doi.org/10.1520/stp12389s
State	Published - 2000

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10.1520/stp12389s

Cite this

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title = "Fracture Toughness of the Ni-Modified A302-B plate of the BR3 Reactor Pressure Vessel.",

abstract = "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.",

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

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AU - Fabry, Albert

AU - van Walle, Eric

AU - Van de Velde, José

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N2 - 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.

AB - 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.

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KW - irradiation

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