Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor.

Sub-channel thermal-hydraulic analysis for VVER- 1000 generation III PWR

The reactor power effect on the consequences pressure waves after LBLOCA in VVER-1000

Analyze the effect of void fraction on the main operating parameters of the VVER-1200

Irradiation Embrittlement of WWER RPV Steels Irradiated at High Fluences

Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core

Estimation of the Reactivity Temperature Coefficients of the AP-1000 Reactor by MCNPX Code

Analysis of Optimum Accident Tolerant Fuel and Cladding Behavior in Advanced Pressurized Water Reactor

Core calculations of the Molten Salt Fast Reactor using different computational codes