Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling

RD Syarifah, Z Su'ud, K Basar, D Irwanto… - … Journal of Energy …, 2018 - Wiley Online Library
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 …

Comparison of thorium nitride and uranium nitride fuel on small modular pressurized water reactor in neutronic analysis using SRAC code

RD Syarifah, MH Aula, A Ardianingrum… - … -European Journal of …, 2022 - papers.ssrn.com
Abstract Comparison of thorium nitride (ThN) and uranium nitride (UN) fuel on small modular
PWR in neutronic analysis has been carried out. PWR in module is one type of reactor that …

Neutronics analysis of UN-PuN fuel for 300MW pressurized water reactor using SRAC-COREBN code

RD Syarifah, AK Sari, A Arkundato… - Eureka: Physics and …, 2022 - papers.ssrn.com
Abstract Nuclear Power Plants (NPP) is one of alternative energy that can be used to
replace fossil energy. NPP is a clean energy that doesn't emit CO2 as a residue from the …

[PDF][PDF] Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code

RD Syarifah, NN MH, Z Hanifah… - Jurnal Jaring SainTek …, 2021 - researchgate.net
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 …

Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor

RD Syarifah, Z Su'ud, K Basar… - Journal of Physics …, 2020 - iopscience.iop.org
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 …

Analysis of the use of thorium in the GFR2400 gas-cooled fast reactor

Y Lima-Reinaldo, JL François… - Nuclear Engineering and …, 2019 - Elsevier
In this work the utilization of thorium in a gas cooled fast reactor was investigated. The study
is based on the reference concept proposed by the French CEA (Commisariat à l'Energie …

Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling

RD Syarifah, Z Su'ud, K Basar… - Journal of Physics …, 2018 - iopscience.iop.org
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 …

Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors

MA Fareha, RD Syarifah, Z Su'ud… - Journal of Physics …, 2018 - iopscience.iop.org
Abstract Design study of long life 600 MWt gas cooled fast reactors which can be operated
for 25 years without refueling or fuel shuffling has been performed. A small Gas-cooled Fast …

Neutronic Analysis for The Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel

TE Angelina, RD Syarifah, N Widiawati… - Journal of Physics …, 2024 - iopscience.iop.org
A neutronic analysis has been carried out for the radial direction heterogeneous core
configuration in GFR with thorium nitride fuel to obtain the most optimal heterogeneous …

A COMPARATIVE ANALYSIS OF GAS-COOLED FAST REACTOR USING HETEROGENEOUS CORE CONFIGURATIONS WITH THREE AND FIVE FUEL …

F Prasetya, RD Syarifah, I Karomah… - … -European Journal of …, 2024 - search.ebscohost.com
GFR or Gas-cooled Fast Reactor is one type of fast generation-IV that uses a very high
cooling temperature. Thus, it is necessary to have the right reactor core design so that the …