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3D analysis of TRISO fuel compacts via X-ray computed tomography

Journal of nuclear materials, 2022-04, Vol.565 (-)

2022

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Versatile TRISO fuel particle modeling in Bison

Nuclear engineering and design, 2024-11, Vol.428, Article 113515

2024

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Neutronic and thermal–hydraulic coupling of FCM and helium annular fuel as accident-tolerant fuel

Nuclear engineering and design, 2024-11, Vol.428, Article 113522

2024

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High uranium loading TRISO particle for microreactor applications

Nuclear engineering and design, 2023-12, Vol.414, p.112628, Article 112628

2023

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Oxide evolution on the SiC layer of TRISO particles during extended air oxidation

Journal of nuclear materials, 2021-11, Vol.558

2021

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APPLICATION OF TWO STAGE METHOD OF CHARACTERISTICS / SP3 METHODOLOGY TO TRISO-FUELLED LEU SPACE REACTOR IN WIMS 11

EPJ Web of conferences, 2021-01, Vol.247, p.1009

2021

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Conceptual Design of the Transformational Challenge Reactor

Nuclear science and engineering, 2022-12, Vol.196 (12), p.1399-1424

2022

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Method for measurement of TRISO kernel and layer volumes by X-ray computed tomography

Journal of nuclear materials, 2020-06, Vol.539 (1)

2020

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Evaluation of the spatial self-shielding impact for TRISO-based nuclear fuel depletion

Nuclear engineering and design, 2023-11, Vol.416

2023

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AGR-2 irradiated TRISO particle IPyC/SiC interface analysis using FIB-SEM tomography

Journal of nuclear materials, 2022-10, Vol.573 (1)

2022

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Fission product distribution in irradiated safety-tested and as-irradiated AGR-2 TRISO particles

Journal of nuclear materials, 2021-12, Vol.559

2021

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Micromechanical properties of TRISO coatings by in-situ high temperature nanoindentation and microcantilever fracture

Journal of the European Ceramic Society, 2024-05, Vol.44 (5), p.3112-3120

2024

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3D analysis of TRISO fuel compacts via X-ray computed tomography

Journal of nuclear materials, 2022-07, Vol.565 (C), p.153745, Article 153745

2022

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Sensitivity analysis and fuel performance of a control rod withdrawal in the generic fluoride-salt-cooled high temperature reactor

Nuclear engineering and design, 2024-11, Vol.428, Article 113529

2024

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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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Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle

Journal of the European Ceramic Society, 2018-09, Vol.38 (12), p.4173-4188

2018

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High-temperature oxidation behavior of the SiC layer of TRISO particles in low-pressure oxygen

Journal of the American Ceramic Society, 2023-02, Vol.106 (6)

2023

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Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON

Nuclear engineering and design, 2018-08, Vol.335 (C), p.116-127

2018

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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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Preparation and high temperature performance of NbC layer in TRISO particles

Journal of the European Ceramic Society, 2022-12, Vol.42 (15), p.6889-6897

2022

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Coated particle fuel: Historical perspectives and current progress

Journal of nuclear materials, 2019-03, Vol.515, p.434-450

2019

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Evaluation of the spatial self-shielding impact for TRISO-based nuclear fuel depletion

Nuclear engineering and design, 2024-01, Vol.416, p.112749, Article 112749

2024

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Thermal conductivity of SiC and PyC coatings in spherical nuclear fuel particles measured by nanosecond time domain thermoreflectance

Journal of the European Ceramic Society, 2024-06, Vol.44 (6), p.3696-3704

2024

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Role of microstructure on CO corrosion of SiC layer in UO₂-TRISO fuel

Journal of nuclear materials, 2020-04, Vol.537 (1)

2020

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Improved measurement of local thermal conductivities of coatings by the steady-state Raman spectroscopy method: A case study in TRISO particles

Journal of the European Ceramic Society, 2024-03, Vol.44 (3), p.1412-1420

2024

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3D analysis of TRISO fuel compacts via X-ray computed tomography

Versatile TRISO fuel particle modeling in Bison

Neutronic and thermal–hydraulic coupling of FCM and helium annular fuel as accident-tolerant fuel

High uranium loading TRISO particle for microreactor applications

Oxide evolution on the SiC layer of TRISO particles during extended air oxidation

APPLICATION OF TWO STAGE METHOD OF CHARACTERISTICS / SP3 METHODOLOGY TO TRISO-FUELLED LEU SPACE REACTOR IN WIMS 11

Conceptual Design of the Transformational Challenge Reactor

Method for measurement of TRISO kernel and layer volumes by X-ray computed tomography

Evaluation of the spatial self-shielding impact for TRISO-based nuclear fuel depletion

AGR-2 irradiated TRISO particle IPyC/SiC interface analysis using FIB-SEM tomography

Fission product distribution in irradiated safety-tested and as-irradiated AGR-2 TRISO particles

Micromechanical properties of TRISO coatings by in-situ high temperature nanoindentation and microcantilever fracture

3D analysis of TRISO fuel compacts via X-ray computed tomography

Sensitivity analysis and fuel performance of a control rod withdrawal in the generic fluoride-salt-cooled high temperature reactor

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

Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle

High-temperature oxidation behavior of the SiC layer of TRISO particles in low-pressure oxygen

Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON

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

Preparation and high temperature performance of NbC layer in TRISO particles

Coated particle fuel: Historical perspectives and current progress

Evaluation of the spatial self-shielding impact for TRISO-based nuclear fuel depletion

Thermal conductivity of SiC and PyC coatings in spherical nuclear fuel particles measured by nanosecond time domain thermoreflectance

Role of microstructure on CO corrosion of SiC layer in UO₂-TRISO fuel

Improved measurement of local thermal conductivities of coatings by the steady-state Raman spectroscopy method: A case study in TRISO particles

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