Small, Modular Advanced High Temperature Reactor-Carbonate Thermochemical Cycle

Holcomb, David Eugene; Ilas, Dan; Middleton, Bobby; Arrieta, Marie

doi:10.2172/1162075

Cited by 2 publications

(2 citation statements)

References 7 publications

(8 reference statements)

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“…Subsequently, a roadmap was prepared describing the remaining FHR principal technology challenges [Holcomb 2013]. ORNL frequently performs technology-readiness-level assessments for the major systems, structures, and components of various designs [Holcomb 2014a andHolcomb 2014b].…”

Section: Functional Areas: Develop Regulatory Review Roadmap and Prototype Research And Test Reactor Guidancementioning

confidence: 99%

Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

Belles¹,

Jain²,

Powers³

2017

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Section: Functional Areas: Develop Regulatory Review Roadmap and Prototype Research And Test Reactor Guidancementioning

confidence: 99%

Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

Belles¹,

Jain²,

Powers³

2017

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“…One objective of the project will be to expand the data base for the thermophysical properties of this particular salt. This salt has also been selected by ORNL as the intermediate loop coolant for the Small Modular Advanced High-Temperature Reactor (SmAHTR) [50], primarily based on its low melting point. The SmAHTR is a small fluoride-salt-cooled high-temperature reactor concept designed to support coupled industrial processes such as hydrogen production.…”

mentioning

confidence: 99%

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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Small, Modular Advanced High Temperature Reactor-Carbonate Thermochemical Cycle

Cited by 2 publications

References 7 publications

Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

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

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