Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview

Qualls, A. L.; Betzler, Benjamin R.; Brown, Nicholas R.; Carbajo, J.J.; Greenwood, Michael S.; Hale, Richard; Harrison, T.; Powers, Jeffrey J.; Robb, Kevin; Terrell, Jerry W.; Wysocki, Aaron; Gehin, Jess C.; Worrall, Andrew

doi:10.1016/j.anucene.2016.11.021

Cited by 31 publications

(10 citation statements)

References 19 publications

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“…Burnups reaching up to 180 GWd/MTHM are intended. Reactivity control is achieved using control rods and blades containing boron carbide (Cisneros 2013, Andreades et al 2014, Qualls et al 2017, Latta et al 2019).…”

Section: Fluoride Salt-cooled High-temperature Reactormentioning

confidence: 99%

Key Nuclear Data Impacting Reactivity in Advanced Reactors

Bostelmann

Ilas

Wieselquist

2020

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Section: Fluoride Salt-cooled High-temperature Reactormentioning

confidence: 99%

Key Nuclear Data Impacting Reactivity in Advanced Reactors

Bostelmann

Ilas

Wieselquist

2020

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“…Salt-cooled concepts of current interest are mainly thermal spectrum concepts that use fluoride salts as the primary coolant. This class of reactor, known as fluoride salt-cooled hightemperature reactors (FHRs), has been the subject of the majority of recent MSR research, including concept design studies at ORNL (Brown et al 2017;Ingersoll et al 2007;Ingersoll 2005;Ingersoll and Forsberg 2004;Qualls et al 2017;Qualls et al 2016). Licensing paths and safeguards for salt-cooled concepts are more analogous to traditionally licensed reactor designs.…”

Section: Criteria For Dynamic Modelsmentioning

confidence: 99%

Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors (Revision 1)

Greenwood

Betzler

Qualls

et al. 2019

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Modeling and SimulationIn modeling the fuel cycle of the MSDR, it is important to appropriately capture the time-dependent change in the isotopic composition of the fuel salt undergoing irradiation, feeding, and processing. The isotopic composition change is a function of the initial composition, flux spectrum, fueling rates, and effective removal rates of important isotopes. While the initial composition, fueling rate, and removal rates are defined, the flux spectrum is obtained from a separate reactor physics calculation.To generate an appropriate time-dependent fuel salt composition, the flux spectrum must represent the average flux spectrum experienced by the salt within the core. Several approaches may be taken to ensure that this is the case: (1) perform depletion using a full-core model, or (2) generate a representative

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“…The PARCS regulatory-grade core simulator was used to perform analyses of steady-state neutronics and thermal hydraulics. The system layout for the FHR-DR is described in some detail in Qualls et al (2016Qualls et al ( , 2017). be nil, which is a conservative assumption that predicts higher fuel temperatures.…”

Section: Fhr Dr Thermal-hydraulic Design and Core Analysismentioning

confidence: 99%

“…This paper is a companion paper to Qualls et al (2017), which presents a high-level overview of a preconceptual design philosophy for a fluoride salt-cooled engineering demonstration reactor. This paper describes details of the reactor core design and preliminary safety analysis for that engineering demonstration reactor.…”

Section: Introductionmentioning

confidence: 99%

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

Brown

Betzler

Carbajo

et al. 2017

Annals of Nuclear Energy

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Engineering demonstration reactors are nuclear reactors built to establish proof of concept for technology options that have never been built. Examples of engineering demonstration reactors include Peach Bottom 1 for high temperature gas-cooled reactors (HTGRs) and Experimental Breeder Reactor II (EBR-II) for sodium-cooled fast reactors. Engineering demonstrations have historically played a vital role in advancing the technology readiness level of reactor technologies. This paper details a preconceptual design for a fluoride salt-cooled engineering demonstration reactor. The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) is a concept for a salt-cooled reactor with 100 megawatts of thermal output (MWt). It would use tristructural-isotropic (TRISO) particle fuel within prismatic graphite blocks. FLiBe (2 7 LiF-BeF 2) is the reference primary coolant. The FHR DR is designed to be small, simple, and affordable. Core design characteristics, fuel cycle performance, and safety analysis of the FHR DR preconcept have been evaluated. The FHR DR core design features a negative or negligible void coefficient throughout a reactor operating cycle. Both single-batch (cartridge) and multiple-batch fuel cycles can be demonstrated in the FHR DR. The single-batch cycle length of the FHR DR core is estimated at between 12-18 months, assuming the successful qualification of composite carbon

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Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview

Cited by 31 publications

References 19 publications

Key Nuclear Data Impacting Reactivity in Advanced Reactors

Key Nuclear Data Impacting Reactivity in Advanced Reactors

Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors (Revision 1)

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

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