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Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

International journal of energy research, 2022-03, Vol.46 (4), p.4852-4868

2022

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Neutronic analysis of thorium nitride and thorium-plutonium nitride fuel for 200 MWth long-life pressurized water reactor

AIP Conference Proceedings, 2021, Vol.2320 (1)

2021

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3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code

Nuclear engineering and design, 2024-08, Vol.425, p.113340, Article 113340

2024

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

International journal of energy research, 2022-06, Vol.46 (7), p.9389-9403

2022

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Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12063

2024

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Neutronic performance of (Th-233U) nitride and oxide for hexagonal tight lattice fuel cell of boiling water reactor

AIP Conference Proceedings, 2023, Vol.2893 (1)

2023

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The effect of radiation source distance to the scintillation detector based on Monte Carlo simulation

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12012

2020

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Neutronic Aspect Assessment on the use of ZrC Triso-Coated Particle (TRIZO) in a High-Temperature Gas-cooled Reactor (HTGR)

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12029

2020

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Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

International journal of energy research, 2021-06, Vol.45 (8), p.12071-12085

2021

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Neutronic Analysis of Lead208-Bismuth Eutectic-Cooled Modified CANDLE Reactor with Core Geometry Variations

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12010

2020

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Conceptual Core Analysis of Long Life PWR Utilizing Thorium-Uranium Fuel Cycle

Journal of physics. Conference series, 2016-08, Vol.739 (1), p.12109

2016

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A passive single-cylindrical neutron spectrometer for photoneutron spectrometry in 10 MV Elekta Precise Linac head

Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2024-08, Vol.1065, p.169519, Article 169519

2024

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Conceptual Analysis of (Th,U-233)O2 Fueled Small Long-Life PWR with Np-237 and Pa-231 as Burnable Poison

Journal of physics. Conference series, 2020-03, Vol.1493 (1)

2020

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Fast Nuclear Reactor Fuel Depletion Analysis Using Fourth Order Runge-Kutta Method

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12014

2020

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Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling

International journal of energy research, 2021-06, Vol.45 (8), p.12317-12324

2021

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Neutronic Analysis of Modular Gas-cooled Fast Reactor for 5-25% of Plutonium Fuel using Parallelization MCNP6 Code

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12008

2020

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Probabilistic Assessment of Severe Accident Consequence in West Bangka

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12032

2017

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Calculation of the binding energy of the lithium nucleus with the yukawa potential and the hellmann potential using WKB approximation

Journal of physics. Conference series, 2019-04, Vol.1204 (1), p.12052

2019

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Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12020

2020

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The development of EASI-based multi-path analysis code for nuclear security system with variability extension

Nuclear Engineering and Technology, 2022, 54(10), , pp.3604-3613

2022

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A Review on the Development of Single-Moderator-Based Neutron Spectrometers

Nuclear technology, 2024-06, p.1-10

2024

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Comparative Study of UO2 and (Th,U-233)O2 Performance in Small Long-Life PWR Fuel Cell

JIF (Jurnal Ilmu Fisika), 2022-10, Vol.15 (1), p.1-12

2022

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Diffusion coefficient calculation of iron in liquid lead using molecular dynamics method with new mixing rule for Lennard-Jones potential parameters

Kuwait journal of science, 2023-07, Vol.50 (3 B), p.1-15

2023

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STUDY ON MCNP6 MODEL IN THE CALCULATION OF KINETIC PARAMETERS FOR PEBBLE BED REACTOR

Acta polytechnica (Prague, Czech Republic : 1992), 2020-01, Vol.60 (2), p.175-184

2020

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

International journal of energy research, 2021-06, Vol.45 (8), p.12272-12283

2021

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Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

Neutronic analysis of thorium nitride and thorium-plutonium nitride fuel for 200 MWth long-life pressurized water reactor

3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code

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

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Neutronic performance of (Th-233U) nitride and oxide for hexagonal tight lattice fuel cell of boiling water reactor

The effect of radiation source distance to the scintillation detector based on Monte Carlo simulation

Neutronic Aspect Assessment on the use of ZrC Triso-Coated Particle (TRIZO) in a High-Temperature Gas-cooled Reactor (HTGR)

Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

Neutronic Analysis of Lead208-Bismuth Eutectic-Cooled Modified CANDLE Reactor with Core Geometry Variations

Conceptual Core Analysis of Long Life PWR Utilizing Thorium-Uranium Fuel Cycle

A passive single-cylindrical neutron spectrometer for photoneutron spectrometry in 10 MV Elekta Precise Linac head

Conceptual Analysis of (Th,U-233)O2 Fueled Small Long-Life PWR with Np-237 and Pa-231 as Burnable Poison

Fast Nuclear Reactor Fuel Depletion Analysis Using Fourth Order Runge-Kutta Method

Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling

Neutronic Analysis of Modular Gas-cooled Fast Reactor for 5-25% of Plutonium Fuel using Parallelization MCNP6 Code

Probabilistic Assessment of Severe Accident Consequence in West Bangka

Calculation of the binding energy of the lithium nucleus with the yukawa potential and the hellmann potential using WKB approximation

Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor

The development of EASI-based multi-path analysis code for nuclear security system with variability extension

A Review on the Development of Single-Moderator-Based Neutron Spectrometers

Comparative Study of UO2 and (Th,U-233)O2 Performance in Small Long-Life PWR Fuel Cell

Diffusion coefficient calculation of iron in liquid lead using molecular dynamics method with new mixing rule for Lennard-Jones potential parameters

STUDY ON MCNP6 MODEL IN THE CALCULATION OF KINETIC PARAMETERS FOR PEBBLE BED REACTOR

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

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