Evaluating the JEFF 3.1, ENDF/B-VII. 0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel

C Wulandari, A Waris, S Permana… - Nuclear Science and …, 2022 - Springer
This study evaluated the nuclear data libraries for a small 100 Mega Watt electric (MWe)
Molten Salt Reactor with plutonium fuel. The reactor has a power output of 100 MWe, which …

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 …

Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor

C Wulandari, N Trianti, S Permana, M Kinoshita… - … Engineering and Design, 2023 - Elsevier
MSR has a unique feature in the fuel system, using liquid salt as fuel, and has flexibility on
material utilization in the fuel, such as Plutonium. Recycling Plutonium into fuel is a good …

Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle

A Amatullah, S Permana, D Irwanto… - Nuclear Engineering and …, 2024 - Elsevier
Abstract The utilization of Small Modular Reactors (SMRs) and micro-reactors holds
significant potential advantages. The primary benefits include their smaller size, accessibility …

Comparative studies on plutonium and minor actinides utilization in small molten salt reactors with various powers and core sizes

A Waris, IK Aji, S Pramuditya, S Permana, Z Su'ud - Energy Procedia, 2015 - Elsevier
Molten salt reactor (MSR) has many advantages such as safety improvement and ability for
waste burning. In the present study, the use of plutonium and minor actinides (MA) in small …

Nuclear energy contribution for net zero emission and national energy mix 2060 in Indonesia

S Permana, N Trianti… - Journal of Physics …, 2022 - iopscience.iop.org
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 …

Basic design analysis of a heavy water-cooled thorium breeder reactor

S Permana - Nuclear Engineering and Design, 2020 - Elsevier
Core design evaluation of heavy water cooled thorium breeding reactor has been
investigated based on optimum basic design criteria such as fuel breeding capability and …

Nitrate salt phase transition study for molten salt loop working fluid consideration

D Hariyanto, S Permana, A Waris, APA Mustari… - Heat and Mass …, 2024 - Springer
Molten salt is an essential topic to study as a working fluid in circulation loop trials.
Experimental and computational studies were presented to analyse the phase transition of …

Experimental and simulation approach of the loop geometry effect on the natural circulation system of the advanced nuclear reactor

D Hariyanto, S Permana… - International Journal of …, 2021 - Wiley Online Library
Lately, natural circulation has become an exciting topic because it has been proposed and
applied in some advanced nuclear reactors as a passive safety system. The aim of the …

Experimental study of thermal behavior of a single-phase natural circulation loop with vertical heater and cooler

D Hariyanto, S Permana - Journal of Physics: Conference Series, 2021 - iopscience.iop.org
The natural circulation systems have been widely applied to various technologies, for
example, safety systems in molten salt reactors. Hence the instability of the natural …