Current understanding of radiation-induced degradation in light water reactor structural materials
K Fukuya - Journal of Nuclear Science and Technology, 2013 - Taylor & Francis
Current phenomenological knowledge and understanding of mechanisms are reviewed for
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …
60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel
JC Van Duysen, GM De Bellefon - Journal of Nuclear Materials, 2017 - Elsevier
The first light water nuclear reactor dedicated to electricity production was commissioned in
Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is …
Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is …
Local approach to fracture based prediction of the ΔT56J and ΔTKIc, 100 shifts due to irradiation for an A508 pressure vessel steel
B Tanguy, C Bouchet, S Bugat, J Besson - Engineering Fracture Mechanics, 2006 - Elsevier
Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitored
using Charpy tests. Reference index temperatures, such as the temperature for which the …
using Charpy tests. Reference index temperatures, such as the temperature for which the …
A wide-range embrittlement trend curve for western reactor pressure vessel steels
M Kirk - Effects of Radiation on Nuclear Materials …, 2013 - asmedigitalcollection.asme.org
Embrittlement trend curves (ETCs) are used to estimate the magnitude of neutron irradiation
embrittlement as a function of both exposure (fluence, flux, temperature,…) and composition …
embrittlement as a function of both exposure (fluence, flux, temperature,…) and composition …
Prediction of the effects of neutron irradiation on the Charpy ductile to brittle transition curve of an A508 pressure vessel steel
C Bouchet, B Tanguy, J Besson, S Bugat - Computational materials science, 2005 - Elsevier
Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitored
using Charpy tests. Reference index temperatures, such as the temperature for which the …
using Charpy tests. Reference index temperatures, such as the temperature for which the …
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 …
Critical review of through-wall attenuation of mechanical properties in RPV steels
CA English, WL Server… - … of Radiation on …, 2004 - asmedigitalcollection.asme.org
This paper reviews the current state of knowledge on attenuation of damage parameters in
reactor pressure vessels (RPVs). There are two methods for evaluating attenuation of …
reactor pressure vessels (RPVs). There are two methods for evaluating attenuation of …
Comparison of predicted transition temperature shifts between static fracture toughness and Charpy-V impact properties due to irradiation for an A508 pressure vessel …
B Tanguy, J Besson, C Bouchet… - ASME Pressure …, 2004 - asmedigitalcollection.asme.org
Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitored
using Charpy tests. Reference index temperatures, such as the temperature for which the …
using Charpy tests. Reference index temperatures, such as the temperature for which the …
Modelling of irradiation embrittlement in the ductile to brittle transition range for an A508 pressure vessel steel
B Tanguy, J Besson, S Bugat - ASME Pressure …, 2006 - asmedigitalcollection.asme.org
The aging behavior of structural steels used to manufacture nuclear pressure vessels is
surveyed using Charpy V-notch specimens located in capsules inside the pressure vessel …
surveyed using Charpy V-notch specimens located in capsules inside the pressure vessel …
Reaction rates measurement across the pressure vessel of Chooz-A PWR by self-dosimetry technique
D Beretz, C Destouches, A Bache - Reactor Dosimetry In The 21st …, 2003 - World Scientific
Abstract CHOOZ-A, a French-Belgian power plant was the first PWR in operation in France;
it was definitively shut down in 1991. A large feedback program has been realized during …
it was definitively shut down in 1991. A large feedback program has been realized during …