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Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor

  • Ercan Yıldız ORCID logo EMAIL logo and Hüsnü Aksakal ORCID logo
Published/Copyright: February 29, 2024
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Kerntechnik
From the journal Kerntechnik Volume 89 Issue 3

Abstract

FLIBE (LiF–BeF2) is both a nuclear reactor coolant and a solvent for fertile or fissile materials. FLIBE can also dissolve a variety of fissile and fertile materials such as uranium, thorium and plutonium and has the ability to serve as liquid fuel for molten salt reactors (MSRs). It’s very high thermal capacity and chemical stability are among its other valuable properties. In addition, the low atomic weights of lithium, beryllium and to a lesser extent fluorine make FLIBE an effective neutron moderator. In this study, cross-section values were determined by using various level density models (constant temperature + Fermi gas, back-shifted Fermi gas, generalized superfluid, microscopic level density models) for reactions of 19F(n, α)16N, 19F(n, p)19O, 35Cl(n, α)32P, 35Cl(n, p)35S and 79Br(n, α)76As, 79Br(n, p)79Se, 127I(n, α)124Sb, 127I(n, p)127Te using TALYS 1.95 code and these datas are compared with the values in the EXFOR database.

Keywords: FLIBE; fusion reactor blanket; molten salt reactor; level density; TALYS
Corresponding author: Ercan Yıldız, Vocational School of Health Services, Kahramanmaraş, Sütçü Imam University, Kahramanmaraş, Türkiye, E-mail:

  1. Research ethics: Not applicable.

  2. Author contributions: E. Yildiz and H. Aksakal both wrote the manuscript text and used the simulation codes to obtain presented results. All the authors reviewed the manuscript.

  3. Competing interests: The authors state no conflict of interest.

  4. Research funding: None declared.

  5. Data availability: All of the data generated or analysed during this study are included in this article. In case, they can also be made available by the corresponding author on reasonable request.

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Received: 2023-10-13
Accepted: 2024-02-08
Published Online: 2024-02-29
Published in Print: 2024-06-25

© 2024 Walter de Gruyter GmbH, Berlin/Boston

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  3. Analyses of the unavailability dynamics of emergency core cooling system
  4. Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
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  10. Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
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https://doi.org/10.1515/kern-2023-0109
Keywords for this article
FLIBE; fusion reactor blanket; molten salt reactor; level density; TALYS

Articles in the same Issue

  1. Frontmatter
  2. Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
  3. Analyses of the unavailability dynamics of emergency core cooling system
  4. Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
  5. Numerical simulation analysis of high-temperature bent sodium heat pipes
  6. Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
  7. Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
  8. Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
  9. Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
  10. Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
  11. A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
  12. CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
  13. Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
  14. Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
  15. Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
  16. Calendar of events
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