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Title: Flibe Use in Fusion Reactors - An Initial Safety Assessment

Abstract

This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF2) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material.

Authors:
;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
USDOE
OSTI Identifier:
911494
Report Number(s):
INEEL/EXT-99-00331
TRN: US0704591
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 - PLASMA PHYSICS AND FUSION TECHNOLOGY; AEROSOLS; BERYLLIUM COMPOUNDS; COOLANTS; COOLING SYSTEMS; FLIBE; FLUORINE; MAGNETIC FIELDS; MOLTEN SALTS; MSRE REACTOR; NEUTRONS; POWER PLANTS; SAFETY; THERMONUCLEAR REACTORS; TOXICITY; TRITIUM; beryllium; chemical toxicity; Flibe; fluorine; fusion power plant; magnetic fields; molten salt coolant; plasma-facing material; safety issues; tritium

Citation Formats

Cadwallader, Lee Charles, and Longhurst, Glen Reed. Flibe Use in Fusion Reactors - An Initial Safety Assessment. United States: N. p., 1999. Web. doi:10.2172/911494.
Cadwallader, Lee Charles, & Longhurst, Glen Reed. Flibe Use in Fusion Reactors - An Initial Safety Assessment. United States. https://doi.org/10.2172/911494
Cadwallader, Lee Charles, and Longhurst, Glen Reed. Thu . "Flibe Use in Fusion Reactors - An Initial Safety Assessment". United States. https://doi.org/10.2172/911494. https://www.osti.gov/servlets/purl/911494.
@article{osti_911494,
title = {Flibe Use in Fusion Reactors - An Initial Safety Assessment},
author = {Cadwallader, Lee Charles and Longhurst, Glen Reed},
abstractNote = {This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF2) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material.},
doi = {10.2172/911494},
url = {https://www.osti.gov/biblio/911494}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {4}
}