Heat-Pipe Heat Exchangers for Salt-Cooled Fission and Fusion Reactors to Avoid Salt Freezing and Control Tritium: A Review
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The fluoride-salt-cooled high-temperature reactor and some proposed fusion reactors use clean fluoride salts as reactor coolants that have melting points above 450°C and generate tritium as discussed by the authors.Abstract:
The fluoride-salt-cooled high-temperature reactor and some proposed fusion reactors use clean fluoride salts as reactor coolants that have melting points above 450°C and generate tritium. Tritium d...read more
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Fusion Blankets and Fluoride-Salt-Cooled High-Temperature Reactors with Flibe Salt Coolant: Common Challenges, Tritium Control, and Opportunities for Synergistic Development Strategies Between Fission, Fusion, and Solar Salt Technologies
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Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook
Dianqiang Jiang,Da-Lin Zhang,Xinyu Li,Shibao Wang,Chenglong Wang,Hao Qin,Yanwen Guo,Wenxi Tian,Guanghui Su,Suizheng Qiu +9 more
TL;DR: In this article , the history and characteristics of FHRs are reviewed, including the concept initiation and active exploration stages, and the research status of the FHR is introduced, which is about the state of the art in primary coolant systems, structural materials, key equipment, energy conversion systems, direct reactor auxiliary cooling systems, nuclear fuel, tritium control strategies, and experimental studies.
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Design of passive residual heat removal systems and application of two-phase thermosyphons: A review
TL;DR: In this paper , the authors conducted a review on the application of two-phase thermosyphons in passive residual heat removal systems (PRHRs) in nuclear power plants.
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Heat Pipe as a Passive Cooling System Driving New Generation of Nuclear Power Plants
TL;DR: In this paper, a new generation of Small Modular Reactor (SMR) in form of Nuclear Micro Reactors (NMR), this type of fission reactor has integrated Alkali metal heat pipes to a series of Stirling convertors or thermoelectric converters for power generation.
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A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications
TL;DR: A critical review of heat pipe (HP) experimental data sets that contain pertinent information regarding nuclear technology that may be beneficial to researchers is provided in this paper , where the authors provide comprehensive information regarding the vast applicability of HPs used in the nuclear industry, including the theory of operation and limitations.
References
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Journal ArticleDOI
Heat pipes in modern heat exchangers
TL;DR: In this paper, a review of heat pipe developments in the former Soviet Union countries is presented, and some new results obtained in USA and Europe are also included in the review. But none of the results are available for the former USSR.
Journal ArticleDOI
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets
Brandon Sorbom,Justin Ball,Timothy R. Palmer,F. J. Mangiarotti,J. M. Sierchio,Paul Bonoli,C.P. Kasten,D.A. Sutherland,Harold Barnard,Christian Bernt Haakonsen,J. Goh,Choongki Sung,Dennis G. Whyte +12 more
TL;DR: The robust, robust, compact (ARC) as discussed by the authors is the product of a conceptual design study aimed at reducing the size, cost and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant.
ReportDOI
Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR)
TL;DR: In this article, the authors presented an assessment of candidate salts proposed as the primary coolant for the Advanced High-Temperature Reactor (AHTR) based upon a review of physical properties, nuclear properties, and chemical factors.
Book ChapterDOI
4.16 – Tritium Barriers and Tritium Diffusion in Fusion Reactors
TL;DR: In this article, the tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials, are presented, along with the parameters necessary for tritium release calculations for various regions of a fusion reactor.
Journal ArticleDOI
Hydrogen transport in stainless steels
TL;DR: In this paper, precise measurements of hydrogen permeability and diffusivity were performed for some stainless steels and high temperature materials utilizing an extremely purified hydrogen under pressure of 0.001-0.1 MPa at temperatures between 500 and 1200 K. Most of the determined values of φ and D give good Arrhenius relationship against inverse temperature.