The tritium breeding and energy absorption in an inertial fusion energy (IFE) reactor chamber have been investigated with variable coolant zone thickness using different materials. Examples are given for HYLIFE-II (an IFE reactor design) and for magnetohydrodynamic (MHD) energy conversion chambers using Flibe (Li2BeF4) as coolant. Investigations related to MHD are extended to the use of LiH, lithium, and Li17-Pb83 eutectic as working fluid. Natural lithium is used in all cases, except in the case of LiPb, for which both natural and enriched options were calculated. To achieve a useful energy density for energy conversion purposes with a sufficient tritium breeding ratio (TBR = 1.1 to 1.2), coolant zone thicknesses must be 25 cm for LiH, 50 ...
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
The water-cooled lithium lead breeding blanket is one of the candidate systems considered for the im...
This study investigates the neutronics design aspects of a hybrid fusion-fission energy system calle...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
Neutronic performance of a blanket driven ICF (Inertial confinement fusion) neutron based on SiCf/Si...
This study investigates the neutronics design aspects of a hybrid fusion-fission energy system calle...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Ista...
In this study, neutronic performance of Lithium Hydride (LiH) material is analyzed in a D-T driven h...
A key technical and economic consideration in the design of the prospective direct drive inertial fu...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
In an inertial fusion energy (FE) thick-liquid chamber design such as HYLEE-II, a molten-salt is use...
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
The water-cooled lithium lead breeding blanket is one of the candidate systems considered for the im...
This study investigates the neutronics design aspects of a hybrid fusion-fission energy system calle...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
Neutronic performance of a blanket driven ICF (Inertial confinement fusion) neutron based on SiCf/Si...
This study investigates the neutronics design aspects of a hybrid fusion-fission energy system calle...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Ista...
In this study, neutronic performance of Lithium Hydride (LiH) material is analyzed in a D-T driven h...
A key technical and economic consideration in the design of the prospective direct drive inertial fu...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
In an inertial fusion energy (FE) thick-liquid chamber design such as HYLEE-II, a molten-salt is use...
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
The water-cooled lithium lead breeding blanket is one of the candidate systems considered for the im...
This study investigates the neutronics design aspects of a hybrid fusion-fission energy system calle...