60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

  title={60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel},
  author={J-C. Van Duysen and J-C. Van Duysen and Gabriel Meric de Bellefon},
  journal={Journal of Nuclear Materials},

An assessment of the available alternatives for fusion relevant neutron sources

The discovery of void swelling in neutron-irradiated stainless steels by Cawthorne and Fulton in 1966 showed that radiation effects would seriously affect the lifetime of fission reactors. A few

Radiation Damage of Reactor Pressure Vessel Steels Studied by Positron Annihilation Spectroscopy—A Review

Safe and long term operation of nuclear reactors is one of the most discussed challenges in nuclear power engineering. The radiation degradation of nuclear design materials limits the operational

Effects of Irradiation and Thermal Ageing on the Nanoscale Chemistry of Steel Welds

Structural materials of nuclear power plants degrade during operation due to thermal ageing and irradiation from the reactor core. Effects on the materials are an increase in hardness and tensile

Nanoindentation of ion-irradiated reactor pressure vessel steels – model-based interpretation and comparison with neutron irradiation

Abstract Ion-irradiation-induced hardening is investigated on six selected reactor pressure vessel (RPV) steels. The steels were irradiated with 5 MeV Fe2+ ions at fluences ranging from 0.01 to 1.0

Effects of Neutron, Ion and Proton Irradiation on Nano-Indentation Hardness of RPV Steels

The irradiation embrittlement damage of reactor pressure vessel (RPV) steel is one of its primary failure mechanisms. In this work, neutron, ion and proton irradiation experiments were carried on the

Measurements of Total Hemispherical Emissivity of A508/A533B Alloy Steel

Abstract The total hemispherical emissivity of A508/A533B alloy steels was measured for conditions of interest in nuclear plant safety. The effect of long-term oxidation on the emissivity of



Simulation of Irradiation Effects in Reactor Pressure Vessel Steels: the Reactor for Virtual Experiments (REVE) Project

Components of commercial nuclear reactors are subjected to neutron bombardments that can modify their mechanical properties. Prediction of in-service and post-service behaviors generally requires

Radiation hardening in magnox pressure-vessel steels

  • S. FisherJ. HarbottleN. Aldridge
  • Materials Science
    Philosophical Transactions of the Royal Society of London. Series A, Mathematical and Physical Sciences
  • 1985
The ferritic steels used for reactor pressure vessels undergo a marked transition from ductile to brittle fracture behaviour over a relatively narrow temperature range. For most unirradiated mild

An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel Materials

There is a general consensus that copper content increases the neutron irradiation sensitivity of reactor vessel materials. Within the past few years, several attempts have been made to introduce