A THERMAL HYDRAULIC MODEL FOR POWER UPGRADING OF WWR-S RESEARCH REACTOR

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

ELECTROMAGNETIC PULSE RESISTANCE OF CONCRETE SHIELDS

Radiological Characterization and Safety during Decommissioning of aNuclear Reactor

"PREDICTION THE PERFORMANCE OF THE IAEA 10 MW MTR RESEARCH REACTOR AT TRANSIENT STARTUP"

Design of portable shield for neutron sources using MCNP Computer Code

Local Materials for Constructing Different Shielda of Nuclear Power Plant

SHIELDING PERFORMANCE OF SUPERCONDUCTING STRUCTURES

Core Physics Analysis of An Assembly of HTTR Reactor using Homogeneous and heterogeneous model.

IRT-1 Research Reactor Decommissioning Preliminary Plan