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Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity

Nuclear Engineering and Technology, 2023, 55(7), , pp.2498-2503

2023

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A newly proposed data assimilation framework to enhance predictions for reflood tests

Nuclear engineering and design, 2022-04, Vol.390, p.111724, Article 111724

2022

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Novel gain-tuning for sliding mode control of second-order mechanical systems: theory and experiments

Scientific reports, 2023-06, Vol.13 (1), p.10541-10541, Article 10541

2023

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Sensitivity and uncertainty analysis of the first core of the DNRR using MCNP6 and new nuclear data libraries

Nuclear engineering and design, 2024-04, Vol.419, p.112986, Article 112986

2024

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Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique

International journal of energy research, 2024-05, Vol.2024, p.1-13

2024

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Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing

Nuclear engineering and design, 2024-03, Vol.418, p.112892, Article 112892

2024

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Output Feedback Control for Spacecraft Attitude System with Practical Predefined-Time Stability Based on Anti-Windup Compensator

Mathematics (Basel), 2023-05, Vol.11 (9), p.2149

2023

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Investigation of the VVER-1000 reactor pressure vessel neutron fluence and displacement per atom using MCNP6

Radiation physics and chemistry (Oxford, England : 1993), 2020-12, Vol.177, p.109141, Article 109141

2020

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Machine Learning Applications and Uncertainty Quantification Analysis for Reflood Tests

Applied sciences, 2024-01, Vol.14 (1), p.324

2024

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Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Science and Technology of Nuclear Installations, 2019, Vol.2019 (2019), p.1-12

2019

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Comments on “Evaluation of neutron radiation damage in the VVER-1200 reactor pressure vessel” by Louis et al. [Radiat. Phys. Chem. 221 (2024): 111738]

Radiation physics and chemistry (Oxford, England : 1993), 2024-10, Vol.223, p.111928, Article 111928

2024

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Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation

Annals of nuclear energy, 2021-10, Vol.161, p.108462, Article 108462

2021

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Application of data assimilation in searching better lattice-physics parameters of fuel assembly

Nuclear engineering and design, 2023-09, Vol.411, p.112415, Article 112415

2023

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A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition

Nuclear engineering and technology, 2024-07

2024

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Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity

Nuclear engineering and technology, 2023, Vol.55 (7), p.2498-2503

2023

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STAR-CCM+ simulation of debris bed formation in the unheated DEFCON-S experiment

Annals of nuclear energy, 2024-10, Vol.206, p.110619, Article 110619

2024

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Determination of Fe and Tb concentrations in geological and environmental samples using the instrumental neutron activation analysis method combined with the γ − γ coincidence technique

Radiation physics and chemistry (Oxford, England : 1993), 2022-11, Vol.200, p.110203, Article 110203

2022

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Modeling of the Dalat Nuclear Research Reactor (DNRR) with the Serpent 2 Monte Carlo code

Nuclear Science and Technology, 2019-09, Vol.9 (3), p.21-29

2019

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Investigation of DPA in the reactor pressure vessel of VVER-1000/V320

Nuclear Science and Technology, 2017-12, Vol.7 (4), p.16-25

2017

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Burnup calculation of the OECD VVER-1000 LEU benchmark assembly using MCNP6 and SRAC2006

Nuclear Science and Technology, 2018-12, Vol.8 (4), p.10-19

2018

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Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Nuclear Science and Technology, 2016-12, Vol.6 (4), p.18-25

2016

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Multi codes and multi-scale analysis for void fraction prediction in hot channel for VVER-1000/V392

Nuclear Science and Technology, 2015-09, Vol.5 (3), p.19-31

2015

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Development of an MCNP5-ORIGEN2 coupling scheme for burnup calculation of VVER-1000 fuel assemblies

Nuclear Science and Technology, 2016-09, Vol.6 (3), p.16-30

2016

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Representative neutronic characteristics calculations for the VVER-1000 reactors using SRAC and MCNP5

Nuclear Science and Technology, 2016-06, Vol.6 (2), p.21-30

2016

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Coulped neutronics/thermal-hydraulics calculation of VVER-1000 fuel assembly

Nuclear Science and Technology, 2016-06, Vol.6 (2), p.31-38

2016

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Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity

A newly proposed data assimilation framework to enhance predictions for reflood tests

Novel gain-tuning for sliding mode control of second-order mechanical systems: theory and experiments

Sensitivity and uncertainty analysis of the first core of the DNRR using MCNP6 and new nuclear data libraries

Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique

Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing

Output Feedback Control for Spacecraft Attitude System with Practical Predefined-Time Stability Based on Anti-Windup Compensator

Investigation of the VVER-1000 reactor pressure vessel neutron fluence and displacement per atom using MCNP6

Machine Learning Applications and Uncertainty Quantification Analysis for Reflood Tests

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Comments on “Evaluation of neutron radiation damage in the VVER-1200 reactor pressure vessel” by Louis et al. [Radiat. Phys. Chem. 221 (2024): 111738]

Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation

Application of data assimilation in searching better lattice-physics parameters of fuel assembly

A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition

Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity

STAR-CCM+ simulation of debris bed formation in the unheated DEFCON-S experiment

Determination of Fe and Tb concentrations in geological and environmental samples using the instrumental neutron activation analysis method combined with the γ − γ coincidence technique

Modeling of the Dalat Nuclear Research Reactor (DNRR) with the Serpent 2 Monte Carlo code

Investigation of DPA in the reactor pressure vessel of VVER-1000/V320

Burnup calculation of the OECD VVER-1000 LEU benchmark assembly using MCNP6 and SRAC2006

Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Multi codes and multi-scale analysis for void fraction prediction in hot channel for VVER-1000/V392

Development of an MCNP5-ORIGEN2 coupling scheme for burnup calculation of VVER-1000 fuel assemblies

Representative neutronic characteristics calculations for the VVER-1000 reactors using SRAC and MCNP5

Coulped neutronics/thermal-hydraulics calculation of VVER-1000 fuel assembly

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