Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)

Zweibaum, Nicolas; Cao, Guoping; Cisneros, Anselmo T.; Kelleher, Brian; Laufer, Michael; Scarlat, Raluca O.; Seifried, Jeffrey E.; Anderson, Mark; Forsberg, Charles W.; Greenspan, E.; Hu, Lin‐Wen; Peterson, Per F.; Sridharan, Kumar

doi:10.1016/j.pnucene.2014.04.008

Cited by 23 publications

(12 citation statements)

References 38 publications

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“…Liquid salts have been identified as excellent candidate heat transport fluids for intermediate loops, supporting several types of advanced high temperature reactors [1,2,3,4]. Liquid salts have also been proposed for use as a primary coolant for the Advanced High Temperature Reactor (AHTR) [5] and the Fluoride Salt-cooled High-Temperature Reactor (FHR) [6,7]. Fluoride salt-coolants are eutectic binary or tertiary mixtures of fluoride salts with melting points in the range of 320 to 500°C.…”

Section: Motivationmentioning

confidence: 99%

“…The high-temperature test section in the liquid salt loop can be used for examination of materials issues, thermal stresses, and heat transfer. Metallic materials have been studied extensively in liquid salt environments [1,2,3], but additional research is needed to evaluate the performance of ceramic and composite materials such as SiC/SiC in liquid salt environments [7]. Fundamental heat transfer issues for liquid salts are related to the fact that these are high-Prandtl-number fluids with high viscosities and specific heats, and relatively low thermal conductivities.…”

Section: Motivationmentioning

confidence: 99%

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Strategic need for a multi-purpose thermal hydraulic loop for support of advanced reactor technologies

O’Brien¹,

Sabharwall²,

Yoon³

et al. 2014

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This report presents a conceptual design for a new high-temperature, multi-fluid, multi-loop test facility for Idaho National Laboratory (INL) to support thermal hydraulic, materials, and thermal energy storage research for nuclear and nuclear-hybrid applications. In its initial configuration, the facility will include a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed with this facility include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs) at prototypical operating conditions, flow and heat transfer issues related to core thermal hydraulics in advanced helium-cooled and salt-cooled reactors, and evaluation of corrosion behavior of new cladding materials and accident-tolerant fuels for light water reactors (LWRs) at prototypical conditions. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. Research performed in this facility will advance the state of the art and technology readiness level of high-temperature IHXs for nuclear applications, while establishing INL as a center of excellence for development and certification of this technology. The thermal energy storage capability will support research and demonstration activities related to process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will assist in development of reliable predictive models for thermal-hydraulic design and safety codes over the range of expected advanced reactor operating conditions. Proposed/existing IHX heat transfer and friction correlations and criteria will be assessed with information on materials compatibility and instrumentation needs. The experimental database will guide development of appropriate predictive methods and be available for code verification and validation (V&V) related to these systems. viii ix ACKNOWLEDGMENTS The authors would like to acknowledge the Laboratory Directed Research and Development Program of the Nuclear System Design and Analysis Division for supporting the development of the advanced reactor technology multipurpose thermal hydraulic loop.

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Section: Motivationmentioning

confidence: 99%

Section: Motivationmentioning

confidence: 99%

Strategic need for a multi-purpose thermal hydraulic loop for support of advanced reactor technologies

O’Brien¹,

Sabharwall²,

Yoon³

et al. 2014

View full text Add to dashboard Cite

show abstract

“…Liquid salts have also been proposed for use as a primary coolant for the Advanced High Temperature Reactor (AHTR) [5] and the Fluoride Salt-cooled High-Temperature Reactor (FHR) [6,7]. Fluoride salt-coolants are eutectic binary or tertiary mixtures of fluoride salts with melting points in the range of 320 to 500°C.…”

Section: Introductionmentioning

confidence: 99%

“…Metallic materials have been studied extensively in liquid salt environments [1][2][3], but additional research is needed to evaluate the performance of ceramic and composite materials such as SiC/SiC in liquid salt environments [7]. Fundamental heat transfer issues for liquid salts are related to the fact that these are highPrandtl-number fluids with high viscosities and specific heats, and relatively low thermal conductivities.…”

Section: Introductionmentioning

confidence: 99%

“…Flow geometries of interest include prototypical prismatic core configurations and pebble beds, as well as heat exchanger flow passages. The high Prandtl number reduces the potential for thermal shock (compared to low-Prandtlnumber liquid metal coolants), but the possibility of large thermal stresses still exists [7]. Bypass flow can also be an issue for prismatic reactor core configurations with liquid salt coolants.…”

Section: Introductionmentioning

confidence: 99%

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Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges

Sabharwall¹,

O’Brien²,

Yoon³

et al. 2015

EPJ Nuclear Sci. Technol.

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Abstract. A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/ steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs) at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750°C), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF 4 ) flow loop operating at low pressure (0.2 MPa), at a temperature of ∼450°C. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift) in measuring operational data for extended periods of times, as data collected will be used for code and model verification and validation, one of the key purposes for the loop. The experimental facility will provide a much-needed database for successful development of advanced reactors and provide insight into the needs and challenges in instrumentation for advanced high-temperature reactors.

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Development, feasibility, and uncertainty of radioactive 22Na tracer dilution and gamma spectroscopy for mass determination of molten salt for pyroprocessing spent nuclear fuels

Cao

Storms²,

Coleman³

et al. 2023

J Radioanal Nucl Chem

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Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)

Cited by 23 publications

References 38 publications

Strategic need for a multi-purpose thermal hydraulic loop for support of advanced reactor technologies

Strategic need for a multi-purpose thermal hydraulic loop for support of advanced reactor technologies

Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges

Development, feasibility, and uncertainty of radioactive 22Na tracer dilution and gamma spectroscopy for mass determination of molten salt for pyroprocessing spent nuclear fuels

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