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A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

Nuclear engineering and technology, 2020-01, Vol.52 (1), p.1-13

2020

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Investigation on radial fuel relocation and its influence on heat split phenomenon of dual-cooled annular fuel element

International Journal of Advanced Nuclear Reactor Design and Technology, 2022-09, Vol.4 (3), p.164-170

2022

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Design and assessment of a core-power controller for lithium-cooled space nuclear reactor based on the concept of fuzzy model predictive control

Frontiers in energy research, 2023-01, Vol.10

2023

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An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code

Nuclear engineering and technology, 2021-04, Vol.53 (4), p.1236-1249

2021

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Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method

Nuclear materials and energy, 2023-09, Vol.36, p.101463, Article 101463

2023

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Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials

Nuclear Engineering and Technology, 2021, 53(1), , pp.178-187

2021

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Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response

Journal of nuclear materials, 2018-08, Vol.507 (C), p.24-37

2018

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Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts

Journal of nuclear materials, 2019-04, Vol.516, p.271-288

2019

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Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation

Journal of nuclear materials, 2022-08, Vol.567, p.153779, Article 153779

2022

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Investigation on axial relocation of fragmented annular fuel under loss of coolant accident conditions with discrete element method

Journal of nuclear materials, 2023-02, Vol.574, p.154159, Article 154159

2023

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Design and evaluation of a high power density and high energy efficiency fuel element for space nuclear reactors

Applied thermal engineering, 2021-06, Vol.191, p.116915, Article 116915

2021

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Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures

Journal of nuclear materials, 2023-12, Vol.587, p.154705, Article 154705

2023

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Creep failure of a solution-annealed 15-15Ti steel exposed to stagnant lead-bismuth eutectic at 550 and 600 °C

Materials science & engineering. A, Structural materials : properties, microstructure and processing, 2020-11, Vol.798, p.140230, Article 140230

2020

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Effect of Si doping on elastic-plastic fracture toughness (JIC) of T91 ferritic/martensitic steel in liquid lead-bismuth eutectic

Materials science & engineering. A, Structural materials : properties, microstructure and processing, 2024-04, Vol.898, p.146405, Article 146405

2024

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Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and -saturated lead-bismuth eutectic at 350°C

Corrosion science, 2020-04, Vol.165, p.108364, Article 108364

2020

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Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors

Nuclear engineering and design, 2020-05, Vol.361, p.110567, Article 110567

2020

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Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 °C

Journal of nuclear materials, 2020-01, Vol.528, p.151859, Article 151859

2020

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Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization

Applied thermal engineering, 2020-06, Vol.173, p.115237, Article 115237

2020

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3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition

Progress in nuclear energy (New series), 2020-08, Vol.126, p.103428, Article 103428

2020

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Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs

Nuclear engineering and design, 2016-05, Vol.301, p.353-365

2016

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Effect of temperature on liquid metal embrittlement susceptibility of an Fe10Cr4Al ferritic alloy in contact with stagnant lead-bismuth eutectic

Journal of nuclear materials, 2020-08, Vol.537, p.152196, Article 152196

2020

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Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs

Annals of nuclear energy, 2017-06, Vol.104, p.146-156

2017

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Neuroprotective effect of Panax notoginseng plysaccharides against focal cerebral ischemia reperfusion injury in rats

International journal of biological macromolecules, 2014-02, Vol.63, p.177-180

2014

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Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels

Progress in nuclear energy (New series), 2020-06, Vol.124, p.103330, Article 103330

2020

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A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code

Progress in nuclear energy (New series), 2018-05, Vol.105, p.51-60

2018

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A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

Investigation on radial fuel relocation and its influence on heat split phenomenon of dual-cooled annular fuel element

Design and assessment of a core-power controller for lithium-cooled space nuclear reactor based on the concept of fuzzy model predictive control

An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code

Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method

Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials

Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response

Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts

Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation

Investigation on axial relocation of fragmented annular fuel under loss of coolant accident conditions with discrete element method

Design and evaluation of a high power density and high energy efficiency fuel element for space nuclear reactors

Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures

Creep failure of a solution-annealed 15-15Ti steel exposed to stagnant lead-bismuth eutectic at 550 and 600 °C

Effect of Si doping on elastic-plastic fracture toughness (JIC) of T91 ferritic/martensitic steel in liquid lead-bismuth eutectic

Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and -saturated lead-bismuth eutectic at 350°C

Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors

Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 °C

Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization

3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition

Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs

Effect of temperature on liquid metal embrittlement susceptibility of an Fe10Cr4Al ferritic alloy in contact with stagnant lead-bismuth eutectic

Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs

Neuroprotective effect of Panax notoginseng plysaccharides against focal cerebral ischemia reperfusion injury in rats

Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels

A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code

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