Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee

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doi:10.2172/441122

Cited by 2 publications

(3 citation statements)

References 7 publications

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“…There are some inherent challenges that arise from being an MSR, such as fluorine generation, uncertainties in the long-term waste form, an absence of a regulatory framework on salt wastes, etc. [2] These challenges are also displayed in the MSRE case.…”

Section: Decommissioning Challengesmentioning

confidence: 97%

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Preconceptual Design of Irradiated Fuel Salt Management System

Joo

2022

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The National Reactor Innovation Center was established by the U.S. Department of Energy to accelerate the demonstration and deployment of advanced nuclear reactors. To meet this mission, the National Reactor Innovation Center has developed the Laboratory for Operations and Testing in the U.S. (LOTUS) to support the first fast-spectrum molten salt reactor demonstration. The goal of this research is to understand the system requirements that may be applied to a molten salt reactor experiment in the LOTUS test bed and to perform systems analyses and preconceptual development of a storage container for the management of the irradiated molten salt fuel. This study proposes a set of irradiated fuel salt management processes for the molten salt reactor, from defueling to storage or disposal. For that, the historic Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory has served as a crucial source of data for a mock application.This paper proposes a potential geometry for storing irradiated fuel salt based on MSRE data and the Monte Carlo N-Particle radiation transport code. The geometry was analyzed for criticality safety under abnormal situations, such as water ingress and interaction between containers. Based on the determined configuration of the storage system, the decay heat produced from the irradiated fuel salts was calculated to provide a reasonable time scale of the dormancy period. Using the same geometry assumed above, the neutron and gamma dose rates from the irradiated fuel salt at the end of the dormancy period were estimated, which will be useful for understanding the handling and radiation protection requirements for handling the irradiated fuel salt.Lastly, a reactor in the LOTUS test bed could use chloride-based fuel as opposed to the fluoridebased fuel used in MSRE. Thus, a literature study provided data to understand the similarities and differences between the characteristics of fluoride-and chloride-based salts in terms of salt chemistry, material characteristics, postirradiation behavior, neutronics, thermal hydraulics, and heat removal. This study, together with the proposed irradiated fuel salt management processes, preliminary criticality calculations, decay heat, and dose rate estimates, provides a strong basis for future investigation into the management of irradiated fuel salts generated during molten salt reactor technology demonstrations.

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Section: Decommissioning Challengesmentioning

confidence: 97%

“…It was an 8-MW-class experimental reactor that operated for 4 years, from 1965 to 1969. [2] Its fuel salt was based on LiF-BeF 2 -ZrF 4 , in which fissile material, UF 4 , was dissolved. It was initially loaded with 218 kg of uranium, of which 30 wt% was U-235 and 70% was U-238.…”

Section: Overview and Operational Historymentioning

confidence: 99%

Preconceptual Design of Irradiated Fuel Salt Management System

Joo

2022

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“…Dehalogenation and conversion to a borosilicate glass are applicable to chloride, fluoride, and mixed halide salts [90]. Dehalogenation accompanied by oxidation has been central to creating stable waste forms from halide-bearing materials for decades [91] and has been considered as an alternative for the stabilization of MSRE fuel and flush salts [92]. In the glass material oxidation and dissolution system, the used fuel salt is introduced into a Pb borate glass melter.…”

Section: Integrated Waste Processingmentioning

confidence: 99%

Integrating the Safety Evaluation for a Molten Salt Reactor Operation and Fuel Cycle Facility Application

Holcomb

Huning

Belles

et al. 2022

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Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Cited by 2 publications

References 7 publications

Preconceptual Design of Irradiated Fuel Salt Management System

Preconceptual Design of Irradiated Fuel Salt Management System

Integrating the Safety Evaluation for a Molten Salt Reactor Operation and Fuel Cycle Facility Application

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