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Testing of a sCVD diamond detection system in the CROCUS reactor

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Testing of a sCVD diamond detection system in the CROCUS reactor

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Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR)

Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme

Cross-section modelling effects on pressurised water reactor main steam line break analyses

On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test

On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations

Mechanical properties-micro structure correlation in neutron irradiated heat-affected zones of austenitic stainless steels

Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples

Application of the shaped electrode technique to a large area rectangular capacitively coupled plasma reactor to suppress standing wave nonuniformity