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Keywords: neutron irradiation
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Proceedings Papers

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A024, July 13–15, 2021
Paper No: PVP2021-61969
... Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-61969 EFFECT OF NEUTRON IRRADIATION ON THE MECHANICAL PROPERTIES OF AN A508 CL2 AND 15KH2NMFA IRRADIATED IN THE NOMAD_3 RIG IN THE BR2 COOLING WATER Inge Uytdenhouwen, Rachid...
Proceedings Papers

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A058, July 13–15, 2021
Paper No: PVP2021-61892
... distribution was investigated in the postulated crack area under the PTS events of unirradiated and highly-neutron irradiated RPV steels. Vickers hardness in heat-affected zone (HAZ) due to stainless overlay cladding and 10 mm from the cladding were higher than that of a quarter thickness position, where...
Proceedings Papers

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A038, August 3, 2020
Paper No: PVP2020-21515
...-CT specimens were available for testing. The main objective of this paper is to measure fracture toughness in the transition and ductile regime before and after irradiation and to compare the results with low flux surveillance data. Keywords: mini-CT, fracture toughness, neutron irradiation...
Proceedings Papers

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A060, August 3, 2020
Paper No: PVP2020-21513
...Abstract Abstract The typical operating temperatures of a nuclear reactor pressure vessel in a PWR is typically between ∼290°C and 300°C. However, many BWRs and some PWRs operate at slightly lower temperatures down to 275°C. Most of the literature and neutron irradiation damage is therefore...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A075, August 3, 2020
Paper No: PVP2020-21365
... . crack growth rate K validity neutron irradiation austenitic stainless steel EVALUATION OF CRACK GROWTH RATE OF NEUTRON IRRADIATED AUSTENITIC STAINLESS STEELS AT HIGH STRESS INTENSITY FACTOR LEVELS Hitoshi Seto1, Masato Koshiishi1, Shigeaki Tanaka2, Ryoji Obata3 1 Nippon Nuclear Fuel Development Co...
Proceedings Papers

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A017, July 14–19, 2019
Paper No: PVP2019-93441
... stainless steels used in reactor internal components are known to show decreases in ductility and fracture toughness due to accumulated neutron irradiation damage. In Japan, Rules on Fitness-for- Service for Nuclear Power Plants of the Japan Society of Mechanical Engineers Code (JSME FFS Code) provides...