An Overview of Liquid Fluoride Salt Heat Transport Systems

Corrosion behavior of ZrC–SiC composite ceramics in LiF–NaF–KF molten salt at high temperatures

“…The molten LiF-KF-NaF eutectic salt (46.5/11.5/42 mol%), commonly referred as FLiNaK, is a leading candidate material for heat transfer fluids because of its superior heat transfer properties [8,9]. FLiNaK molten salts can be used as a secondary coolant and a primary simulation coolant in molten salt reactors (MSRs) [10,11].…”

Advanced High Temperature Reactor Systems and Economic Analysis

“…7,8,9 For this baseline AHTR concept, 2 7 LiF-BeF 2 (enriched in 7 Li to 99.995%), referred to as FLiBe, was selected for the primary coolant because it has the most favorable nuclear properties, including a negative void coefficient and low activation enabling easier primary system maintenance. A 47% KF 53% ZrF 4 (mole percent) fluoride salt mixture was chosen for the intermediate loop as a compromise among heat transfer performance, melting temperature, and cost.…”

The Comparison of (n,p), (n,α), (n,2n) and (α,n) Reaction Cross-Sections for 7Li and 9Be Target Nuclei

“…Formulas obtained from this systematics have been used in the present study for Li and Be target nuclei irradiated with neutrons and alphas. Li and Be elements are candidate materials to be used as advanced blanket materials in fusion reactors [17,18]. Lithium (Li) never occurs freely in nature, instead, it appears only in ionic compounds.…”

“…Neutron and proton distributions of Li and Beisotopes were studied using the new Skyrme-force parameters by Baldik et al [22]. Tel et al [23] made a study of [8][9][10][11][12][13][14][15][16][17][18] Be isotopes using as a neutron multiplier in reactor design using HartreeFock approximation. The calculations of double-differential neutron emission cross sections for 9 Be target nucleus at 14.2 MeV neutron energy has been investigated by Ş ahan et al [24].…”