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Nuclear Science and Engineering Volume 143, 2003 - Issue 1
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Technical Paper

A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The Cinsf1D Code

David LecarpentierElectricité de France Research and Development, département SINETICS 1 avenue du général De Gaulle, 92141 Clamart Cedex, France
&
Vincent CarpentierElectricité de France Research and Development, département SINETICS 1 avenue du général De Gaulle, 92141 Clamart Cedex, France
Pages 33-46 | Published online: 10 Apr 2017

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Aaron J. Reynolds & Todd S. Palmer. (2023) An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment. Nuclear Science and Engineering 197:1, pages 45-73.
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Daniel Wooten & Jeffrey J. Powers. (2018) A Review of Molten Salt Reactor Kinetics Models. Nuclear Science and Engineering 191:3, pages 203-230.
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Kun Zhuang, Youqi Zheng, Liangzhi Cao, Tianliang Hu & Hongchun Wu. (2017) Improvements and validation of the transient analysis code MOREL for molten salt reactors. Journal of Nuclear Science and Technology 54:8, pages 878-890.
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Kun Zhuang, Liangzhi Cao, Youqi Zheng & Hongchun Wu. (2015) Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design. Journal of Nuclear Science and Technology 52:2, pages 251-263.
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J. Kópházi, D. Lathouwers & J. L. Kloosterman. (2009) Development of a Three-Dimensional Time-Dependent Calculation Scheme for Molten Salt Reactors and Validation of the Measurement Data of the Molten Salt Reactor Experiment. Nuclear Science and Engineering 163:2, pages 118-131.
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J. Kópházi, G. Légrádi, S. Czifrus & S. Fehér. (2007) Effect of fuel mixing phenomena on the kinetic behavior of molten salt reactors. Transport Theory and Statistical Physics 36:1-3, pages 227-240.
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S. Dulla & P. Ravetto. (2007) Interactions between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems. Nuclear Science and Engineering 155:3, pages 475-488.
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