The mixture LiF-ThF4-UF4-PuF3 (77.5–6.6-12.3–3.6 mol%), a fuel option for the Molten Salt Fast Reactor (MSFR), has been measured by differential scanning calorimetry (DSC) for determination of phase transitions, and by Knudsen effusion mass spectrometry (KEMS) for measurement of partial vapour pressures. The boiling point of the mixture was determined by extrapolation of total vapour pressure to 1 bar. Thermodynamic calculations were performed and compared with the experimental results. Novel experimental data on pure plutonium trifluoride are presented: melting point, vaporization enthalpy, vapour pressure and ionization energies by electron impact.RST/Reactor Physics and Nuclear Material
A thermodynamic description of the LiF-CeF3-ThF4 system is made in this study using a two-sublattice...
In previous studies a thermodynamic description of the LiF¿NaF¿KF¿RbF¿CsF¿LaF3 system was presented....
The Molten Salt Reactor (MSR) has been selected as one of the Generation IV nuclear systems. The ver...
The mixture LiF-ThF4-UF4-PuF3 (77.5–6.6-12.3–3.6 mol%), a fuel option for the Molten Salt Fast React...
The mixture LiF-ThF4-UF4-PuF3 (77.5e6.6-12.3e3.6 mol%), a fuel option for the Molten Salt Fast React...
A selected composition of the initial fuel of the Molten Salt Fast Reactor (MSFR) is assessed by dif...
PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrog...
The LiF-ThF4-PuF3-UF4 system is the reference salt mixture considered for the Molten Salt Fast React...
The LiF–ThF4–PuF3–UF4 system is the reference salt mixture considered for the Molten Salt Fast React...
In the framework of the new generation of nuclear fission reactors, one of the promising systems is ...
AbstractThe LiF–ThF4–PuF3–UF4 system is the reference salt mixture considered for the Molten Salt Fa...
Phase equilibria in the ThF4-PuF3 system were measured by differential scanning calorimetry. Samples...
PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrog...
The molten salt reactor (MSR) is one of the six reactor concepts of the Generation IV initiative, a...
Molten salt reactor (MSR) concepts are based on using a molten salt mixture as a primary nuclear rea...
A thermodynamic description of the LiF-CeF3-ThF4 system is made in this study using a two-sublattice...
In previous studies a thermodynamic description of the LiF¿NaF¿KF¿RbF¿CsF¿LaF3 system was presented....
The Molten Salt Reactor (MSR) has been selected as one of the Generation IV nuclear systems. The ver...
The mixture LiF-ThF4-UF4-PuF3 (77.5–6.6-12.3–3.6 mol%), a fuel option for the Molten Salt Fast React...
The mixture LiF-ThF4-UF4-PuF3 (77.5e6.6-12.3e3.6 mol%), a fuel option for the Molten Salt Fast React...
A selected composition of the initial fuel of the Molten Salt Fast Reactor (MSFR) is assessed by dif...
PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrog...
The LiF-ThF4-PuF3-UF4 system is the reference salt mixture considered for the Molten Salt Fast React...
The LiF–ThF4–PuF3–UF4 system is the reference salt mixture considered for the Molten Salt Fast React...
In the framework of the new generation of nuclear fission reactors, one of the promising systems is ...
AbstractThe LiF–ThF4–PuF3–UF4 system is the reference salt mixture considered for the Molten Salt Fa...
Phase equilibria in the ThF4-PuF3 system were measured by differential scanning calorimetry. Samples...
PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrog...
The molten salt reactor (MSR) is one of the six reactor concepts of the Generation IV initiative, a...
Molten salt reactor (MSR) concepts are based on using a molten salt mixture as a primary nuclear rea...
A thermodynamic description of the LiF-CeF3-ThF4 system is made in this study using a two-sublattice...
In previous studies a thermodynamic description of the LiF¿NaF¿KF¿RbF¿CsF¿LaF3 system was presented....
The Molten Salt Reactor (MSR) has been selected as one of the Generation IV nuclear systems. The ver...