A coupled heat transfer and tritium mass transport model for a double-wall heat exchanger design for FHRs

Zhang, Dingkang; Wu, Xiao; Shi, Shanbin; Sun, Xiaodong; Christensen, Richard N.; Yoder, G.L.

doi:10.1016/j.anucene.2018.08.039

Cited by 10 publications

(2 citation statements)

References 19 publications

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“…They also analyze potential materials for use as a tritium permeation barrier coating, considering tritium permeability, diffusivity, and solubility. Similarly, Zhang et al designed and modeled a double-walled heat exchanger for use in an FHR or MSR, coupling a tritium transport model to a heat transport model [284]. Although an experimental setup has never been completed before, it is worth noting the theoretical and computational models that have been utilized in modeling these important auxiliary systems for both FHRs and MSRs.…”

Section: Tritium Modelingmentioning

confidence: 99%

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Clark¹,

Luxat²,

Higgins³

et al. 2020

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Section: Tritium Modelingmentioning

confidence: 99%

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Clark¹,

Luxat²,

Higgins³

et al. 2020

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“…In the United States, most recent work on doublewall heat exchangers for flibe systems has been done at the University of Michigan 50,51 and the University of California/Kairos Power. A schematic of a double-wall heat exchanger tube is in Fig.…”

Section: Vd3b Double-wall Heat Exchangersmentioning

confidence: 99%

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

et al. 2019

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Recent developments in high-magnetic-field fusion systems have created large incentives to develop flibe (Li 2 BeF 4) salt fusion blankets that have four functions: (1) convert the high energy of fusion neutrons into heat for the power system, (2) convert lithium into tritium-the fusion fuel, (3) shield the magnets against radiation, and (4) cool the first wall that separates the plasma from the salt blanket. Flibe is the same coolant proposed for fluoride-salt-cooled high-temperature reactors that use clean flibe coolant and graphite-matrix coated-particle fuel. Flibe is also the coolant proposed for some molten salt reactors (MSRs) where the fuel is dissolved in the coolant. The multiple applications for flibe as a coolant create large incentives for cooperative fusion-fission programs for development of the underlying science, design tools, technology (pumps, instrumentation, salt purification, materials, tritium removal, etc.), and supply chains. Other high-temperature molten salts are being developed for alternative MSR systems and for advanced Gen-III concentrated solar power (CSP) systems. The overlapping characteristics of flibe salt with these other salt systems create significant incentives for cooperative fusion-fission-solar programs in multiple areas. We describe the fission and fusion flibe-cooled systems, what has created this synergism, what is different and the same between fission and fusion in terms of using flibe, and the common challenges. We review (1) the characteristics of flibe salts, (2) the status of the technology, (3) the options for tritium capture and control in the salt, heat exchangers, and secondary heat transfer loops, and (4) the coupling to power cycles with heat storage. The technology overlap between flibe systems and other high-temperature MSR and CSP salt systems is described. This defines where there are opportunities for cooperative programs across fission, fusion, and CSP salt programs.

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Performance evaluation of decay heat removal systems of Fluoride-salt-cooled High-temperature Reactor (FHR)

Nakata

Ogura

Miwa

et al. 2019

Annals of Nuclear Energy

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A coupled heat transfer and tritium mass transport model for a double-wall heat exchanger design for FHRs

Cited by 10 publications

References 19 publications

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

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

Performance evaluation of decay heat removal systems of Fluoride-salt-cooled High-temperature Reactor (FHR)

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