Comparison of uranium plutonium nitride and thorium nitride fuel for 500 MWth gas‐cooled
fast reactor has been done. Gas‐cooled fast reactor is one type of generation IV reactor that …

The fuel volume fraction analysis has been carried out with uranium carbide in Gas-Cooled
Fast Reactor using the SRAC Code (Standard Reactor Analysis Code). This code was …

This study has made a calculation of Actinide Minor Addition on Uranium Plutonium Nitride
Fuel for Modular Gas Cooled Fast Reactor. The purpose of this study was to determine the …

Neutronic analysis of UN-PuN fuel use FI-ITB-CHI code for 500MWth GFR longlife without
refuelling has been done. The reactor use fast neutron spectrum, helium coolant and …

Nuclear data libraries playian important role in the accuracy of neutronic aspect calculations,
which determine various factors in a nuclear reactor design. Likewise, deterministic or Monte …

Nuclear power has progressive improvement in the operating performance of exiting
reactors and ensuring economic competitiveness of nuclear electricity around the world. The …

The use of OpenMC code needs to be validated with other code, so that an accurate and
valid criticality value is generated. The validation value is affected by the minimum number …

Abstract Helium Gas Turbine System (HGTS) has compact and simple configuration, and
can make full use of high temperature heat source to achieve high power generation …

Abstract The Molten Salt Reactor (MSR) is a type of reactor in which coolant and fuel are
blended with liquid salts. Liquid fuel enhances heat transfer and temperature control …

As the demand for nuclear energy keeps rising, Generation IV reactor designs continuously
improve. One such potential reactor design is the Gas-cooled Reactor. Neutronic analysis is …