EFFECTS OF DEUTERIUM–LITHIUM FUSION REACTION ON INTERNAL TRITIUM BREEDING

2010 ◽  
Vol 19 (11) ◽  
pp. 2123-2132
Author(s):  
M. MAHDAVI ◽  
B. JALALY
Keyword(s):  
Inertial Confinement Fusion ◽  
Initial Temperature ◽  
Fusion Reaction ◽  
Time Dependent ◽  
Inertial Confinement ◽  
Tritium Breeding ◽  
Dynamical Equations ◽  
Fuel Pellets ◽  
Runge Kutta Method ◽  
Confinement Fusion

The optimal usage of designed fuel pellets is one of the very important parameters in inertial confinement fusion (ICF) systems. In this research, time-dependent dynamical equations for D/D fuel are written by considering impurity of 6 Li . Then dependency of gain on temperature, density and pellet radius is studied using Runge–Kutta method. The obtained results show that the energy gain will be maximized at the initial temperature 35 keV, density, 5000 g/cm3 and ratio impurity of 6 Li , 0.05.

scholarly journals Numerical simulation of implosion and burn of D–T ignitor/D3He fuel pellet for D3He inertial confinement fusion reactor

1993 ◽  
Vol 11 (1) ◽  
pp. 137-147 ◽  
Author(s):  
H. Nakashima ◽  
M. Shinohara ◽  
Y. Wakuta ◽  
T. Honda ◽  
Y. Nakao ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Fusion Reactor ◽  
Coupling Efficiency ◽  
Fuel Pellet ◽  
Parameter Study ◽  
Inertial Confinement ◽  
Liquid Density ◽  
Fuel Pellets ◽  
Confinement Fusion ◽  
R Value

A parameter study of implosion, burn, and gain of D–T ignitor/D3He fuel pellets is presented for a D3He inertial confinement fusion reactor. It is found from burn simulation that attaining a quasi-isobaric state with a temperature of 4 keV and pR value of 2.5 g/cm2 for the D–T ignitor and 0.8 keV and 9.5 g/cm2 for the D3He main fuel would suffice to obtain a pellet gain of ∼40–50 required for the D3He reactor. With 30-MJ laser irradiation and the coupling efficiency of 10%, the density of the target is assumed to be imploded to 5,000 times the liquid density. However, in the implosion simulation to realize the above configuration it is found that after void closure the central hot D–T ignitor region is ignited, while the bulk of the D3He main fuel is still imploding with high velocities. This preignition of the D–T ignitor leads to a low compression of the main fuel and prevents the D–T/D3He pellet from obtaining the required pellet gain. The pellet gain obtained is only ∼3.

Angular radiation temperature simulation for time-dependent capsule drive prediction in inertial confinement fusion

2015 ◽  
Vol 22 (2) ◽  
pp. 022709 ◽  
Author(s):  
Longfei Jing ◽  
Shaoen Jiang ◽  
Dong Yang ◽  
Hang Li ◽  
Lu Zhang ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Time Dependent ◽  
Radiation Temperature ◽  
Inertial Confinement ◽  
Confinement Fusion

scholarly journals Synergism in inertial confinement fusion: a total direct energy conversion package

1989 ◽  
Vol 7 (3) ◽  
pp. 449-466 ◽  
Author(s):  
M. A. Prelas ◽  
E. J. Charlson
Keyword(s):  
Energy Conversion ◽  
Inertial Confinement Fusion ◽  
Fusion Reaction ◽  
Inertial Confinement ◽  
Fusion Reactions ◽  
Direct Energy Conversion ◽  
Transport Length ◽  
Confinement Fusion ◽  
Direct Energy ◽  
Energy Conversion Devices

The products of fusion reactions have unique properties which can be used for direct energy conversion. These products are neutrons and ions. Neutrons can be transported very long distances through solid materials and can interact with certain elements which have a very high absorption cross section. Ions on the other hand have a very short transport length even in a gaseous medium. It is possible to utilize these products in an inertial confinement fusion reactor with two different direct energy conversion devices: a nuclear-pumped laser using neutrons from the fusion reaction; a photon generator material combined with a photovoltaic converter using the ionic fusion products.It will be argued that a nuclear-pumped laser can be more efficient than a conventional laser. It will also be shown that an advanced energy conversion concept based on photon production and photovoltaics can produce ICF system efficiencies of 56%.

scholarly journals Analysis of the retrograde hydrogen boron fusion gains at inertial confinement fusion with volume ignition

1997 ◽  
Vol 15 (4) ◽  
pp. 565-574 ◽  
Author(s):  
Chr. Scheffel ◽  
R.J. Stening ◽  
H. Hora ◽  
R. Höpfl ◽  
J.M. Martinez-Val ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Fusion Reaction ◽  
Relativistic Correction ◽  
Stopping Power ◽  
Inertial Confinement ◽  
Optimum Temperature ◽  
Power Stations ◽  
Confinement Fusion ◽  
Nuclear Fusion Reaction ◽  
Volume Ignition

The very clean nuclear fusion reaction of hydrogen and boron-11 by inertial confinement arrives at conditions for power stations by volume ignition only at compressions to 100,000 times the solid state. The earlier (numerically) observed anomaly of decreasing gain at increasing density (retrograde behavior) is analyzed and the reason clarified: the strong stopping power mechanism, based on Gabor's collective model, is reaching its limit of too small Debye lengths at the extremely high densities because of the optimum temperature in the range of 30 keV due to the reabsorption of the bremsstrahlung. The relativistic correction of the bremsstrahlung for the always much higher temperatures after volume ignition is included from Maxon's model.

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