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Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

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Methodology of Fuel Burn Up Fitting in VVER-1000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations

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Neutron-irradiation hardening in irons and ferritic steels

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Photofission Analysis for Fissile Dosimeters Dedicated to Reactor Pressure Vessel Surveillance

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