Analysis of variation minor actinide pin configurations Np-237, AM-241, and Cm-244 in UN-PuN fueled pressurized water reactor
RD Syarifah, M Nasrullah, F Prasetya… - EUREKA: Physics …, 2024 - journal.eu-jr.eu
Actinide minor is a reactor waste with high toxicity and a long half-life. Minor actinides can
be reduced by reusing them as fuel mixtures in reactors. This research uses PWR reactors …
be reduced by reusing them as fuel mixtures in reactors. This research uses PWR reactors …
Validation of OpenMC Code Criticality Value Calculation for GFR Reactor with UN-PuN Fuel
F Prasetya, AM Mabruri, I Karomah… - Journal of Physics …, 2024 - iopscience.iop.org
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 …
valid criticality value is generated. The validation value is affected by the minimum number …
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 …
cooling temperature. Thus, it is necessary to have the right reactor core design so that the …
Neutronic Analysis on Molten Salt Reactor (MSR) Using OpenMC Code With Variations of Geometry Core Fueled By LiF-BeF2-UF4
RD Syarifah, BA Putri, IK Aji - El-Cezeri, 2024 - dergipark.org.tr
Nuclear Power Plant can produce electricity more efficiently and have low carbon emissions.
The nuclear reactor used in this study is the MSR (Molten Salt Reactor) FUJI-12. This study …
The nuclear reactor used in this study is the MSR (Molten Salt Reactor) FUJI-12. This study …
Comparative Analysis of Hexagonal and Square Fuel Pin Geometry Designs of GFR using Uranium Carbide Fuel
MR Maulana, RD Syarifah, F Prasetya… - Journal of Energy …, 2024 - jemit.fmipa.unila.ac.id
Abstract Comparative Analysis of Hexagonal and Square GFR Fuel Pin Geometry Designs
with Uranium Carbide Fuel has been carried out. Nuclear reactors from Generation I to IV …
with Uranium Carbide Fuel has been carried out. Nuclear reactors from Generation I to IV …
[PDF][PDF] Eastern-European
The charcoal briquette industry faces the problem of the method for determining the drying
stop during its production. The combustion method as the main method is time-consuming …
stop during its production. The combustion method as the main method is time-consuming …