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Andrei Rineiski
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Journal Articles

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Claude Jamond, Elena Martin Lopez, Xue-Nong Chen, Nathalie Girault, Pierre Gubernatis, Andrei Rineiski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011325.
Paper No: NERS-20-1142
https://doi.org/10.1115/1.4052489
Published Online: December 14, 2021
View Article titled, Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection
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Topics: Fuels, Heat transfer, Modeling, Natural convection, Heat, Temperature, Flux (Metallurgy)
Journal Articles

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Andrei Rineiski, Clément Mériot, Marco Marchetti, Jiri Krepel, Christine Coquelet-Pascal, Haileyesus Tsige-Tamirat, Francisco Álvarez-Velarde, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011322.
Paper No: NERS-20-1130
https://doi.org/10.1115/1.4052588
Published Online: October 29, 2021
View Article titled, ESFR-SMART Core Safety Measures and Their Preliminary Assessment
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Topics: Fuels, Safety, Sodium, Sodium fast reactors, Design, Accidents
Proceedings Papers

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Liancheng Guo, Andrei Rineiski
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81841
https://doi.org/10.1115/ICONE26-81841
View Paper titled, Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters
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Topics: Modeling, Simulation, Accidents, Vessels, Coolants, Fuels, Sodium, Sodium fast reactors, Fast neutron reactors, Fluid dynamics
Proceedings Papers

COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR

Dalin Zhang, Zhi-Gang Zhai, Andrei Rineiski, Zhangpeng Guo, Chenglong Wang, Yao Xiao, Suizheng Qiu
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A019, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30609
https://doi.org/10.1115/ICONE22-30609
View Paper titled, COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR
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Topics: Thermal hydraulics, Fuels, Neutrons, Flow (Dynamics), Flux (Metallurgy), Molten salt reactors, Temperature, Vortices, Fast neutron reactors, Numerical analysis
Proceedings Papers

Decay Heat Benchmark for Uranium-Free Fuels With Minor Actinides

Andrei Rineiski, Ge´rald Rimpault, Georgios Glinatsis, Nadia Messaoudi, Sandro Pelloni, Aleksandra Schwenk-Ferrero, Maria Carmen Vicente
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 217-226, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29654
https://doi.org/10.1115/ICONE18-29654
View Paper titled, Decay Heat Benchmark for Uranium-Free Fuels With Minor Actinides
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Topics: Fuels, Heat, Uranium, Bearings, Design, Cooling, Safety, Uncertainty
Proceedings Papers

Transient Analyses for a Molten Salt Transmutation Reactor Using the Extended SIMMER-III Code

Shisheng Wang, Andrei Rineiski, Werner Maschek, Victor Ignatiev
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 91-99, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89209
https://doi.org/10.1115/ICONE14-89209
View Paper titled, Transient Analyses for a Molten Salt Transmutation Reactor Using the Extended SIMMER-III Code
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Topics: Accidents, Equations of state, Fast neutron reactors, Flow (Dynamics), Fuels, Modeling, Molten salt reactors, Neutrons, Spacetime, Transient analysis