Development of advanced blanket performance under irradiation and system integration through JUPITER-II project

Preliminary Tritium Management Design Activities at ORNL

“…Beryllium can be added to FLiBe to increase the ratio of T 2 to TF either as a metal (powder or rod) or as a carbide. This has the advantage of not affecting the chemical or physical properties of the molten salt (Abe et al 2008, and the consumption rate is relatively slow . In systems flushed with hydrogen, as the partial pressure of H 2 increases, HT is more thermodynamically stable than TF and can also drive the conversion to the diatomic gas.…”

Review of stellarator/heliotron design issues towards MFE DEMO

“…This blanket design has encouraged and initiated the Flibe blanket R&D activities as international collaborations [23].…”

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].…”