Results 211 to 220 of about 1,037,219 (260)

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
openaire   +1 more source

The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor

Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, 2018
In thermal Molten Salt Reactors, the nuclear graphite core is in direct contact with the molten salt coolant. Due to the porous nature of nuclear graphite, the molten salt may infiltrate the nuclear graphite, which may affect the mechanical strength and irradiation behavior of the nuclear graphite.
Zhoutong He, Hui Tang, Can Zhang, Yantao Gao, Huihao Xia, Xingtai Zhou   +5 more
openaire   +1 more source

Hybrib Spectrum Molten Salt Reactor

2014
The Molten Salt Reactor (MSR) concept has a unique feature, if compared to the majority of other reactor designs, that its fuel is liquid. This property creates, on one hand, several technical challenges; on the other hand, it offers flexibility in shaping and designing of the active core.
J. Krepel, K. Mikityuk, B. Hombourger, A. Pautz, ZANETTI, MATTEO, AUFIERO, MANUELE, LUZZI, LELIO   +6 more
openaire   +2 more sources

Molten Salt for Molten Salt Reactors (MS4MSRs)

This thesis presents a comprehensive thermodynamic investigation of alternative molten salt systems for use in both thermal- and fast-spectrum molten salt reactors (MSRs). The work integrates new experimental data with advanced thermodynamic modelling to establish a consistent and validated database for both fluoride- and chloride-based fuel ...
openaire   +1 more source

Modelling Frozen Salt Films in a Molten Salt Fast Reactor

Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, 2018
Molten salt reactors are a very promising option for the development of highly innovative solutions for the nuclear energy production of the future. The techniques used to model thermal hydraulics of a molten salt fast reactor when frozen salt wall technology is applied to the core vessel wall are presented here for 2D numerical models of a hyperboloid
Cartland-Glover, G.M., Rolfo, S., Skillen, A.; id_orcid 0000-0003-2364-0054, Emerson, D.R., Moulinec, C., Litskevich, D., Merk, Bruno   +6 more
openaire   +1 more source

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.
openaire   +1 more source

The case for the thorium molten salt reactor

AIP Conference Proceedings, 2012
Shortcomings of current PWR and BWR, solid uranium-fuel, nuclear power reactors are summarized. It is shown how the Molten Salt Reactor (MSR) created and operated at Oak Ridge National Laboratory (ORNL), USA (1960s–1970s) and developed as FUJI reactor by Furukawa and collaborators (1980s–1990s), addresses all of these shortcomings.
E. D. Greaves, K. Furukawa, L. Sajo-Bohus, H. Barros   +3 more
openaire   +1 more source

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.
openaire   +1 more source

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 ...
openaire   +1 more source

Alloys for molten-salt reactors

2015
?????????????????? ???????????????????? ???????????????????????? ???? ????????????, ???????????????????? ?? ???????????????????????? ?????????????????????????????? ???????????????????? ?????? ?????????????? ???????????????????? ?????????????????? ???????? ??????????-?????????????? ?????????????????? ?? ???????????????????????? ??????????????, ??????????
Azhazha, V.M., Bakai, A.S., Lavrinenko, S.D., Bobrov, Yu.P., V???yugov, P.N., Kovtun, K.V., Pylypenko, M.M., Savchenko, V.I., Solopikhin, A.D., Stetsenko, S.P., Malykhin, D.G.   +10 more
openaire   +1 more source