Warm PreStress effect on highly irradiated reactor pressure vessel steel
J Hure, C Vaille, P Wident, D Moinereau… - Journal of Nuclear …, 2015 - Elsevier
This study investigates the Warm Prestress (WPS) effect on 16MND5 (A508 Cl3) RPV steel,
irradiated up to a fluence of 13· 10 23 n. m-2 (E> 1 MeV) at a temperature of 288° C …
irradiated up to a fluence of 13· 10 23 n. m-2 (E> 1 MeV) at a temperature of 288° C …
Experience gained in reactor pressure vessel surveillance programs in France
P Todeschini, L Pineau… - Workshop on …, 2018 - asmedigitalcollection.asme.org
This paper describes the methodology of the French surveillance program as well as some
aspects of the experience gained during its progress. Its main uses in the structural integrity …
aspects of the experience gained during its progress. Its main uses in the structural integrity …
A New Method for Determining the Criterion Level of Impact Energy for Reactor Pressure Vessel Metal
S Kotrechko, K Soroka, V Revka - Available at SSRN 5079377 - papers.ssrn.com
The paper presents the results of approbation of a novel approach for finding the criterion
level of impact energy to estimate a ductile to brittle transition temperature for ferrite and …
level of impact energy to estimate a ductile to brittle transition temperature for ferrite and …