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Journal Articles

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.

Paper No: NERS-21-1137

DOI: https://doi.org/10.1115/1.4052719

Published Online: December 14, 2021

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Topics: Carbon, Collaboration, Economics , Energy consumption, Heat, Hydrogen, Industrial capacity, Innovation, Manufacturing systems, Molten salt reactors

Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.

Paper No: NERS-20-1207

DOI: https://doi.org/10.1115/1.4051612

Published Online: October 19, 2021

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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature

Journal Articles

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508.

Paper No: NERS-20-1152

DOI: https://doi.org/10.1115/1.4050478

Published Online: May 26, 2021

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Topics: Coolants, Fast neutron reactors, Fuels, Gas cooled reactors, High temperature, Liquid metals, Molten salt reactors, Pressurized water reactors, Small modular reactors, Licensing

Journal Articles

A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit

Terry J. Price, Ondrej Chvala

ASME J of Nuclear Rad Sci. January 2021, 7(1): 014501.

Paper No: NERS-19-1126

DOI: https://doi.org/10.1115/1.4046909

Published Online: October 1, 2020

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Topics: Fuels, Molten salt reactors, Steady state, Bubbles

Journal Articles

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Terry Price, Zack Taylor, Ondrej Chvala

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041302.

Paper No: NERS-19-1107

DOI: https://doi.org/10.1115/1.4046258

Published Online: June 3, 2020

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Topics: Bubbles, Fuels, Molten salt reactors, Porosity, Pressure, Nuclear fission, Flow (Dynamics), Pumps

Journal Articles

Xenon Behavior in Molten Salt Reactor Graphite

Terry J. Price, Ondrej Chvala, Zack Taylor

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041303.

Paper No: NERS-19-1115

DOI: https://doi.org/10.1115/1.4046356

Published Online: June 3, 2020

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Topics: Graphite, Molten salt reactors, Diffusion (Physics), Mass transfer

Journal Articles

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

Indarta Kuncoro Aji, Tokushima Tatsuya, Motoyasu Kinoshita, Tomio Okawa

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021105.

Paper No: NERS-19-1051

DOI: https://doi.org/10.1115/1.4045180

Published Online: January 29, 2020

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Topics: Cylinders, Molten salt reactors, Temperature, Valves, Brass (Metal), Thermal conductivity, Melting, Computer simulation, Copper, Fuels

Journal Articles

A Review of Molten Salt Reactor Xenon Analysis Literature

T. J. Price, O. Chvala

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011202.

Paper No: NERS-19-1008

DOI: https://doi.org/10.1115/1.4044746

Published Online: November 29, 2019

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Topics: Molten salt reactors, Graphite, Bubbles, Mass transfer, Fuels, Porosity

Journal Articles

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210.

Paper No: NERS-18-1087

DOI: https://doi.org/10.1115/1.4043813

Published Online: September 3, 2019

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Topics: Fuels, Graphite, Mass transfer, Molten salt reactors, Bubbles, Diffusion (Physics)

Journal Articles

Breeding Properties Study on High-Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011003.

Paper No: NERS-17-1151

DOI: https://doi.org/10.1115/1.4041272

Published Online: January 24, 2019

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Topics: Fuels, Molten salt reactors, Nuclides, Security, Temperature, Transients (Dynamics), Fluids, Nuclear fission, Graphite

Journal Articles

New Exploration on TMSR: Redesign of the TMSR Lattice

J. K. Zhao, S. Y. Si, Q. C. Chen, H. Bei

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011008.

Paper No: NERS-17-1187

DOI: https://doi.org/10.1115/1.4041192

Published Online: January 24, 2019

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Topics: Design, Fuels, Graphite, Optimization, Molten salt reactors, Neutrons, Cladding systems (Building), Safety

Journal Articles

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiří Křepel, Konstantin Mikityuk, Andreas Pautz

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011009.

Paper No: NERS-14-1038

DOI: https://doi.org/10.1115/1.4026401

Published Online: February 9, 2015

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Topics: Equilibrium (Physics), Fuels, Graphite, Molten salt reactors, Neutrons, Nuclear fuel cycle, Design, Nuclear fission, Uranium

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NARROW

Guest Editorial by Gilles Rodriguez

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Small Modular Reactors: Learning From the Past

A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Xenon Behavior in Molten Salt Reactor Graphite

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

A Review of Molten Salt Reactor Xenon Analysis Literature

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Breeding Properties Study on High-Power Thorium Molten Salt Reactor

New Exploration on TMSR: Redesign of the TMSR Lattice

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

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