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Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Science and Technology of Nuclear Installations, 2022-12, Vol.2022, p.1-12

2022

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Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

Nuclear science and techniques, 2021-08, Vol.32 (8), p.110-121, Article 88

2021

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Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme

Annals of nuclear energy, 2013-10, Vol.60, p.383-395

2013

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A benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars technique at 14 MeV

EPJ Web of Conferences, 2023, Vol.284, p.7002

2023

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Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor

Journal of nuclear science and technology, 2012-02, Vol.49 (2), p.222-229

2012

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Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor

International journal of energy research, 2022-03, Vol.46 (4), p.5152-5164

2022

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

Nuclear engineering and design, 2024-03, Vol.418, p.112934, Article 112934

2024

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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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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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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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Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident

Progress in nuclear energy (New series), 2023-08, Vol.162, p.104782, Article 104782

2023

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Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme

Nuclear engineering and design, 2024-06, Vol.422, p.113163, Article 113163

2024

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Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

Nuclear engineering and design, 2023-10, Vol.412, p.112463, Article 112463

2023

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Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme

Kerntechnik (1987), 2023-10, Vol.88 (5), p.566-576

2023

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Burnup Characteristics of a Peu à Peu Fuel Loading Scheme in a 110 MWt Simplified Pebble Bed Reactor

Journal of nuclear science and technology, 2011-11, Vol.48 (11), p.1385

2011

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Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling

International journal of energy research, 2018-01, Vol.42 (1), p.214-220

2018

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Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer

Kerntechnik (1987), 2023-08, Vol.88 (4), p.503-517

2023

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The prediction of helium gas viscosity under high pressure and high temperature with the Chapman-Enskog solution and excess viscosity

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12008

2017

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Charged Particle Flow Base On Mesoscale Simulation With Coupling MPCD-MD Method In Two Dimension Channel

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12011

2017

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Comparative Analysis on Nuclear Fuel Sustainability Aspect of FBR

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12006

2017

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Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12004

2017

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Comparison of Monte Carlo calculation methods for effective delayed neutron fraction

Annals of nuclear energy, 2010-10, Vol.37 (10), p.1308-1315

2010

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Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12022

2017

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Prediction of Melting Penetration of Armco Iron by Liquid Uranium Using MPS_LER

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12019

2017

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Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme

A benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars technique at 14 MeV

Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor

Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor

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

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

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

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

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

Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident

Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme

Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme

Burnup Characteristics of a Peu à Peu Fuel Loading Scheme in a 110 MWt Simplified Pebble Bed Reactor

Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling

Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer

The prediction of helium gas viscosity under high pressure and high temperature with the Chapman-Enskog solution and excess viscosity

Charged Particle Flow Base On Mesoscale Simulation With Coupling MPCD-MD Method In Two Dimension Channel

Comparative Analysis on Nuclear Fuel Sustainability Aspect of FBR

Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12

Comparison of Monte Carlo calculation methods for effective delayed neutron fraction

Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling

Prediction of Melting Penetration of Armco Iron by Liquid Uranium Using MPS_LER

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