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
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 …
Molten Salt Reactor with plutonium fuel. The reactor has a power output of 100 MWe, which …
Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel
Abstract Molten Salt Reactors offer fuel flexibility, allowing the use of different starting fuels,
including U-233, U-235, and Pu-239. U-233 is not a fissile nuclide that is commercially …
including U-233, U-235, and Pu-239. U-233 is not a fissile nuclide that is commercially …
Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor
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 …
material utilization in the fuel, such as Plutonium. Recycling Plutonium into fuel is a good …
Natural Uranium Utilization in FUJI-U3 Molten Salt Reactor
C Wulandari, A Sofyan, A Waris… - Journal of Physics …, 2021 - iopscience.iop.org
Abstract Molten Salt Reactor (MSR) is one of the next-generation nuclear power systems
known as Generation IV. In this paper, the FUJI-U3 MSR type is designed for neutronic …
known as Generation IV. In this paper, the FUJI-U3 MSR type is designed for neutronic …
Numerical Simulation of the Effect of Molten Salt Channel Number on Temperature Distribution in the Molten Salt Core Reactor
A Dwiyulianti, A Yonanda, R Safitri… - Journal of Physics …, 2024 - iopscience.iop.org
A critical aspect in the design of a nuclear reactor that needs to be considered is thermal
analysis. This parameter relates to molten salt circulation, which serves as a fuel, and …
analysis. This parameter relates to molten salt circulation, which serves as a fuel, and …
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 …
[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 …