Preliminary lightweight core design analysis of a micro‐transportable gas‐cooled thermal reactor

C Guan, X Chai, T Zhang, X Liu - International Journal of …, 2022 - Wiley Online Library
Micro nuclear reactors with small sizes have a wide range of applications. The present study
discusses the lightweight core design for a micro‐transportable gas‐cooled thermal reactor …

Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor

S Islam, MT Ahmed - Annals of Nuclear Energy, 2025 - Elsevier
This study investigates the neutronics characterization of the Allegro-75 MW th modular
reactor by analyzing three alternative heterogeneous core configurations-axial, radial, axial+ …

Investigation of the possibility of using a uranium–zirconium metal alloy as a fuel for nuclear power plant AP-1000

AA Galahom, MAE Abdel-Rahman… - … Engineering and Design, 2023 - Elsevier
This paper provides a deep analysis of the possibility of utilizing uranium–zirconium metallic
alloys as Accident Tolerant Fuel (ATF) in the AP-1000 nuclear power reactor. MCNPX 2.7 …

Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code

H Raflis, Z Su'ud, A Waris… - International Journal of …, 2022 - Wiley Online Library
This paper discusses design selection with variation of the height‐to‐diameter (H/D) ratios
and core‐blanket configuration for a long‐life modular gas‐cooled fast reactor (GFR). The …

Simulation of SN transport equation for hexagonal-z reactor using the COMSOL Multiphysics software

Y Wang, J Chen, D Li, L Shi, H Chi, Y Ma - Nuclear Engineering and Design, 2024 - Elsevier
Detailed neutron transport simulation has undergone much investigation in advanced
reactor engineering, where the adaptability of complex geometrics and the simplicity of …

[HTML][HTML] Evaluation of reflector design of ALLEGRO refractory core

P Pónya, C Ding, S Czifrus, E Shwageraus - Annals of Nuclear Energy, 2024 - Elsevier
The core design concept for Gas-cooled Fast Reactors (GFR) is currently under
development. In this paper, the reflector design for the 75 MW refractory core of GFR …

Irregular pentagon loop for nuclear reactor natural circulation system test apparatus

D Hariyanto, S Permana, A Waris, APA Mustari… - … Engineering and Design, 2024 - Elsevier
The natural circulation loop has become a crucial topic for investigating a heat transfer
system without a recirculation pump. This study aimed to analyze the steady-state condition …

Analysis of core configuration for conceptual gas Cooled Fast Reactor (GFR) using OpenMC

I Karomah, AM Mabruri, RD Syarifah… - … Teknologi Reaktor Nuklir …, 2023 - jurnal.batan.go.id
This study focused on a conceptual core configuration of Gas Cooled Fast Reactor (GFR), as
part of a generation IV reactor. Uranium-plutonium carbide (UC-PuC) was used as reactor …

A neutronic comparative study of reflectors in radially and axially heterogeneous cores for the ABR-1000 sodium cooled fast reactor

MHH Niloy, MT Ahmed, FI Farha - Annals of Nuclear Energy, 2025 - Elsevier
In continuation of previous research work, this study investigated the neutronic behavior of
ABR-1000 using OpenMC simulations with nine different reflector materials in axial 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 …