Fluoride Salt-Cooled High-Temperature Reactor Technology Development and Demonstration Roadmap

Holcomb, David Eugene; Flanagan, G.F.; Mays, G.T.; Pointer, W. D.; Robb, Kevin; Yoder, G.L.

doi:10.2172/1107839

Cited by 42 publications

(42 citation statements)

References 38 publications

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“…The FHR offers a convenient technological bridge between today's reactors (solid fuel, water cooled) and future molten salt reactors (liquid fuel, liquid salt cooled). Detail information on the FHR status, operation performance, and current designs can be found in a report …”

Section: Introductionmentioning

confidence: 99%

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Zhang

2019

Energy Tech

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The fluoride salt‐cooled high‐temperature reactor (FHR) is one of the Gen. IV reactor concepts. Considering the complexity of salt chemistry, radiation risk, impurity‐induced material corrosion, and impurity‐induced solid precipitation, the salt chemistry should be well controlled. Therefore, molten salt cleanup systems are needed in operation. Based on the experience of molten salt reactors (MSRs) and available data, the present study identifies the types of impurities, their potential sources, and their impact in FHR primary coolants. Cleanup methods for each type of impurity and future research activities are also discussed.

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Section: Introductionmentioning

confidence: 99%

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Zhang

2019

Energy Tech

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“…Especially, MSR can be designed either in a thermal-spectrum Th-U breeder cycle, which can extend the fuel resources to a large extend. 6 It adopts low-pressure liquid salt and high-temperature coated particle fuel. 3 Compared with other fourth generation reactors, no solid fuel is necessary to be fabricated or used.…”

Section: Introductionmentioning

confidence: 99%

Review of conceptual design and fundamental research of molten salt reactors in China

Zhang

Liu

et al. 2018

Int J Energy Res

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Summary Molten salt reactor (MSR) as 1 candidate of the generation IV advanced nuclear power systems attracted more attention in China due to its top ranked in fuel cycle and thorium utilization. Two types of MSR concepts were studied and developed in parallel, namely the MSR with liquid fuel and that with solid fuel. Abundant fundamental research including the neutronics modeling, thermal‐hydraulics modeling, safety analysis, material investigation, molten salts technologies etc. were carried out. Some analysis software such as COUPLE and FANCY were developed. Several experimental facilities like high‐temperature fluoride salt experiment loop have been constructed. Some passive residual heat removal systems were designed, and 1 test facility is under construction. The key MSR techniques including the extraction and separation of molten salt and construction of N‐base alloy have been mastered. Based on these fundamental research, Chinese Academy of Sciences has completed the design of thorium‐based MSRs with solid fuel and liquid fuel and is promoting their construction in the near future. In China, future efforts should be paid to the material, online fuel processing, Th‐U fuel cycle, component design, and construction and thermal‐hydraulic experiments for MSR, which are rather challenging nowadays.

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“…In Japan, THORIMS‐NES concept and several loop experiments were performed by Furukawa for production of fissile U233 . In 2013, US researchers created an initial technology development roadmap for fluoride salt‐cooled high‐temperature reactors (FHRs) by combining a high temperature gas‐cooled reactor and MSR to improve the affordability of nuclear power . Further, the Chinese Academy of Sciences carried out “Thorium Molten Salt Reactor (TMSR) Nuclear Energy System” project to design Liquid‐Fuel TMSR (TMSR‐LF) and Solid‐Fuel TMSR in the next 20–30 years based on effective utilization of thorium, as shown in Figure…”

Section: Introductionmentioning

confidence: 99%

Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

et al. 2017

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SummaryA molten salt reactor (MSR) is characterized by simultaneously using liquid fuel salt as both the nuclear fuel and coolant. The redistribution of delayed neutron precursors (DNPs) makes the transient behavior of MSRs different from traditional solid-fuel reactors. In this study, a 3D coupled neutronics/thermal hydraulics code, MOREL2.0, was employed to analyze a liquid-fuel Thorium Molten Salt Reactor (TMSR-LF) under perturbations of fuel pump start-up and coast-down and by overheating and overcooling the inlet fuel temperature. Some transient processes were simulated to provide guidance for the future design and optimization of TMSR-LFs. In response to the perturbations, reactivity was lost and gained in the pump start-up and coast-down, respectively.Overheating the inlet fuel temperature introduced negative reactivity, and TMSR-LF maintained a safety state, while overcooling the inlet fuel temperature resulted in positive reactivity. Overcooling by 70 K produced a supercritical transient condition and a rapid increase in power within a short period, which was followed by a decrease in power due to negative temperature feedback. The transient results demonstrate that the negative temperature feedback coefficients guarantee TMSR-LF inherent safety and the variation range of temperature stay within the safety margin.

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Fluoride Salt-Cooled High-Temperature Reactor Technology Development and Demonstration Roadmap

Cited by 42 publications

References 38 publications

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Review of conceptual design and fundamental research of molten salt reactors in China

Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

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