Results 321 to 330 of about 52,960 (385)

MOLTEN-SALT CONVERTER REACTORS

Annals of Nuclear Energy, 1975
Abstract Molten-salt reactors appear to have substantial promise as advanced converters. Conversion ratios of 0.85 – 0.9 should be attainable with favorable fuel cycle costs, with 235U valued at $12/g. An increase in 235U value by a factor of two or three ($10–$30/lb. U3O3, $75/SWU) would be expected to increase the optimum conversion ratio, but this
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Molten salt reactors

Abstract Chapter 18 discusses the development of molten-salt reactors (MSRs) that were initially pursued by Alvin Weinberg at Oak Ridge National Laboratory, with the first MSR becoming critical in 1954. Advantages identified for MSRs included elimination of pressurization equipment that is required for water-cooled reactors and the ...
Yafei Wang, Changzu Zhu, Mingyang Zhang, Wentao Zhou   +3 more
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Molten-Salt Reactor Chemistry

Nuclear Applications and Technology, 1970
This document summarizes the large program of chemical research and development which led to selection of fuel and coolant compositions for the Molten-Salt Reactor Experiment (MSRE) and for subsequent reactors of this type. Chemical behavior of the LiF-BeF2-ZrF4-UF4 fuel mixture and behavior of fission products during power operation of MSRE are ...
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Preface: Molten-Salt Reactors

Nuclear Applications and Technology, 1970
(1970). Preface: Molten-Salt Reactors. Nuclear Applications and Technology: Vol. 8, No. 2, pp. 105-105.
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Liquid Salt Applications and Molten Salt Reactors

Revue Générale Nucléaire, 2007
In the last 5 years, there has been a rapid growth in interest in the use of high-temperature (700 to 1000°C) molten and liquid fluoride salts as coolants and for other functions in nuclear systems. This interest is a consequence of new applications for high-temperature heat and the development of new reactor concepts.
Charles W. Forsberg, C. Renault, C. Le Brun, E. Merle-Lucotte, V. Ignatiev   +4 more
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Fuel Salt for the Molten-Salt Reactor

Atomic Energy, 2013
The solubility of Th, U, Ce, La, and Pr in melted salt 45LiF–12NaF–43KF, which supports a fast neutron spectrum for the molten-salt reactor, is found experimentally to be high in the interval 550–700°C. On the basis of an analysis of the physicochemical and nuclear-physical properties of different fluoride salts, it is proposed that the eutectic 46 ...
L. I. Ponomarev, M. B. Seregin, A. P. Parshin, S. A. Mel’nikov, A. A. Mikhalichenko, L. P. Zagorets, R. N. Manuilov, A. A. Rzheutskii   +7 more
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Analysis of burnup performance and temperature coefficient for a small modular molten-salt reactor started with plutonium

Nuclear Science and Techniques, 2023
Xueliang Zhao, Y. Zou, Rui Yan, X. Cai
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The Molten Salt Reactor Adventure

Nuclear Science and Engineering, 1985
A personal history of the development of molten salt reactors in the United States is presented.
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Study on the effect of thermal deformation on the liquid seal of high-temperature molten salt pump in molten salt reactor

Nuclear Science and Techniques, 2023
Xing-Chao Shen, Yuan Fu, Jian-Yu Zhang
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Design considerations of the supercritical carbon dioxide Brayton cycle of small modular molten salt reactor for ship propulsion

Progress in nuclear energy (New series), 2023
Won-Keun Lee, Sunghyun Yoo, Dong Kyou Park, Kwon-Yeong Lee   +3 more
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