A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor
O Kabach, A Chetaine, A Benchrif… - … Journal of Energy …, 2021 - Wiley Online Library
High‐temperature gas‐cooled reactors (HTGRs) present an interesting concept for the next
generation of nuclear reactors due to them having many advantages. In particular, their fuel …
generation of nuclear reactors due to them having many advantages. In particular, their fuel …
Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle
Abstract The utilization of Small Modular Reactors (SMRs) and micro-reactors holds
significant potential advantages. The primary benefits include their smaller size, accessibility …
significant potential advantages. The primary benefits include their smaller size, accessibility …
Nuclear energy contribution for net zero emission and national energy mix 2060 in Indonesia
Indonesian Government has strongly announcement to the public which is in line with the
Paris Agreement that has been signed and ratified with other 164 countries across the globe …
Paris Agreement that has been signed and ratified with other 164 countries across the globe …
Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power
The use of zirconium carbide (ZrC) as a substitute for silicon carbide (SiC) has been
proposed to improve the performance of coated particles for high‐temperature gas‐cooled …
proposed to improve the performance of coated particles for high‐temperature gas‐cooled …
Comparison of Neutronic Analysis for 250 MWth Molten Salt Reactor using Monte Carlo OpenMC Code with Different Nuclear Data Libraries of JENDL 5.0, ENDF/B …
M Variastuti, D Irwanto - Journal of Physics: Conference Series, 2024 - iopscience.iop.org
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 …
which determine various factors in a nuclear reactor design. Likewise, deterministic or Monte …
Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor
M Variastuti, D Irwanto - Journal of Physics: Conference Series, 2024 - iopscience.iop.org
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 …
blended with liquid salts. Liquid fuel enhances heat transfer and temperature control …
Effective Multiplication Factor Analysis of Gas-cooled Reactor using OpenMC code with ENDF/B-VII. 1, ENDF/B-VIII. 0 and JENDL-5.0 Nuclear Data
MAI Rachmat, D Irwanto - Journal of Physics: Conference Series, 2024 - iopscience.iop.org
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 …
improve. One such potential reactor design is the Gas-cooled Reactor. Neutronic analysis is …
Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006
A Amatullah, S Permana… - Journal of Physics …, 2024 - iopscience.iop.org
One strategy for emission reduction in Indonesia is the dedieselization program, replacing
diesel power plants with renewables. Pressurized Water Reactor (PWR) type Small Modular …
diesel power plants with renewables. Pressurized Water Reactor (PWR) type Small Modular …
[PDF][PDF] Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor.
M Variastuti, D Irwanto, MN Subkhi… - Trends in Sciences, 2023 - researchgate.net
The power peaking factor (PPF) is an important parameter that needs to be considered to
maintain the reactor's stability, safety and efficiency. The present study discusses the power …
maintain the reactor's stability, safety and efficiency. The present study discusses the power …
Study on fissile material usage for 50 MWt high temperature gas reactor using (Pu-U) O2 fuel
AL Pratama, D Irwanto - Journal of Physics: Conference Series, 2021 - iopscience.iop.org
One of the most potential nuclear power plants is High Temperature Gas-cooled Reactor
(HTGR). It is a reactor system designed using TRISO (Tristructural-Isotropic) coated fuel and …
(HTGR). It is a reactor system designed using TRISO (Tristructural-Isotropic) coated fuel and …