scholarly journals Nonlinear force driven plasma blocks igniting solid density hydrogen boron: Laser fusion energy without radioactivity

2009 ◽  
Vol 27 (3) ◽  
pp. 491-496 ◽  
Author(s):  
H. Hora ◽  
G.H. Miley ◽  
N. Azizi ◽  
B. Malekynia ◽  
M. Ghoranneviss ◽  
...  

AbstractEnergy production by laser driven fusion energy is highly matured by spherical compression and ignition of deuterium-tritium (DT) fuel. An alternative scheme is the fast ignition where petawatt (PW)-picosecond (ps) laser pulses are used. A significant anomaly was measured and theoretically analyzed with very clean PW-ps laser pulses for avoiding relativistic self focusing. This permits a come-back of the side-on ignition scheme of uncompressed solid DT, which is in essential contrast to the spherical compression scheme. The conditions of side-on ignition thresholds needed exorbitantly high energy flux densities E*. These conditions are now in reach by using PW-ps laser pulses to verify side-on ignition for DT. Generalizing this to side-on igniting solid state density proton-Boron-11 (HB11) arrives at the surprising result that this is one order of magnitude more difficult than the DT fusion. This is in contrast to the well known impossibility of igniting HB11 by spherical laser compression and may offer fusion energy production with exclusion of neutron generation and nuclear radiation effects with a minimum of heat pollution in power stations and application for long mission space propulsion.

2008 ◽  
Vol 26 (1) ◽  
pp. 105-112 ◽  
Author(s):  
M. Ghoranneviss ◽  
B. Malekynia ◽  
H. Hora ◽  
G.H. Miley ◽  
X. He

AbstractFast ignition for fusion energy by using petawatt-picosecond (PW-ps) laser pulses was modified due to an anomaly based on extremely clean suppression of prepulses. The resulting plasma blocks with space charge neutral ion current densities above 1011Amp/cm2may be used to ignite deuterium-tritium at densities at or little above solid state density. The difficulty is to produce extremely high energy flux densities of the blocks. Results are reported how the threshold can be reduced by a factor up to fife if the inhibition factor for thermal conductivity due to electric double layers is included in the hydrodynamic analysis.


2014 ◽  
Vol 2014 ◽  
pp. 1-14 ◽  
Author(s):  
M. Ghoranneviss ◽  
A. Salar Elahi

Discovery of the laser in 1960 hopes were based on using its very high energy concentration within very short pulses of time and very small volumes for energy generation from nuclear fusion as “Inertial Fusion Energy” (IFE), parallel to the efforts to produce energy from “Magnetic Confinement Fusion” (MCF), by burning deuterium-tritium (DT) in high temperature plasmas to helium. Over the years the fusion gain was increased by a number of magnitudes and has reached nearly break-even after numerous difficulties in physics and technology had been solved. After briefly summarizing laser driven IFE, we report how the recently developed lasers with pulses of petawatt power and picosecond duration may open new alternatives for IFE with the goal to possibly ignite solid or low compressed DT fuel thereby creating a simplified reactor scheme. Ultrahigh acceleration of plasma blocks after irradiation of picosecond (PS) laser pulses of around terawatt (TW) power in the range of 1020 cm/s2was discovered by Sauerbrey (1996) as measured by Doppler effect where the laser intensity was up to about 1018 W/cm2. This is several orders of magnitude higher than acceleration by irradiation based on thermal interaction of lasers has produced.


2009 ◽  
Vol 27 (2) ◽  
pp. 233-241 ◽  
Author(s):  
B. Malekynia ◽  
M. Ghoranneviss ◽  
H. Hora ◽  
G.H. Miley

AbstractThe anomaly at laser plasma interaction at laser pulses of TW to PW power and ps duration led to a very unique generation of quasi-neutral plasma blocks by a skin layer interaction avoiding the relativistic self-focusing. This is in contrast to numerous usual experiments. The plasma blocks have ion current densities above 1011A/cm2and may be used for a fast ignition scheme with comparably low compression of the deuterium tritium (DT) fuel. The difficulty is that a very high energy flux densityE* of the ions is necessary according to the hydrodynamic theory (Bobin, 1971, 1974; Chu, 1972). This theory did not include the later discovered collective effect for the stopping power of the alpha particles. One problem is being discussed, whether the Bethe-Bloch binary collision theory or the collective collision theory of Gabor has to be applied. The inclusion of the collective effect results in a reduction of the threshold value ofE* for ignition by a factor of about fife.


2021 ◽  
Vol 13 (1) ◽  
pp. 59-70
Author(s):  
Vladimir I. Vysotskii ◽  
◽  
Alla A. Kornilova ◽  
Mykhaylo V. Vysotskyy ◽  
◽  
...  

The paper considers the features and quantitative characteristics of the first successful laser experiments on the formation of a thermonuclear plasma and registration of neutrons in nuclear fusion reactions under pulsed irradiation of a LiD crystal. Quantitative analysis shows that the production of neutrons recorded in these experiments is not associated with thermonuclear reactions in hot laser plasma. The most probable mechanism of neutron generation is associated with nuclear reactions at low energies and is due to the formation of coherent correlated states (CCS) of deuterons. In this experiment, such states can be formed in two different processes: due to the effect of a shock wave in the undisturbed part of the target lattice on the vibrational state of deuterium nuclei or when deuterium nuclei with energy of about 500 eV move in the lattice. This part of the deuterium nuclei corresponds to the high-energy "tail" of the Maxwellian distribution of the total flux of particles entering from the laser plasma into the interplanar channel. In this second case, the process of the formation of the CCS is associated with the longitudinal periodicity of the interplanar crystal channel, which is equivalent to a nonstationary oscillator in the own coordinate system of moving particle. The expediency of repeating these experiments is shown, in which, in addition to neutrons, one should expect a more efficient generation of other nuclear fusion products due to low-energy reactions involving lithium isotopes from the target composition.


2013 ◽  
Vol 06 ◽  
pp. 85-116 ◽  
Author(s):  
R. O. Bangerter ◽  
A. Faltens ◽  
P. A. Seidl

Since the 1970s, high energy heavy ion accelerators have been one of the leading options for imploding and igniting targets for inertial fusion energy production. Following the energy crisis of the early 1970s, a number of people in the international accelerator community enthusiastically began working on accelerators for this application. In the last decade, there has also been significant interest in using accelerators to study high energy density physics (HEDP). Nevertheless, research on heavy ion accelerators for fusion has proceeded slowly pending demonstration of target ignition using the National Ignition Facility (NIF), a laser-based facility at Lawrence Livermore National Laboratory. A recent report of the National Research Council recommends expansion of accelerator research in the US if and when the NIF achieves ignition. Fusion target physics and the economics of commercial energy production place constraints on the design of accelerators for fusion applications. From a scientific standpoint, phase space and space charge considerations lead to the most stringent constraints. Meeting these constraints almost certainly requires the use of multiple beams of heavy ions with kinetic energies >1 GeV. These constraints also favor the use of singly charged ions. This article discusses the constraints for both fusion and HEDP, and explains how they lead to the requirements on beam parameters. RF and induction linacs are currently the leading contenders for fusion applications. We discuss the advantages and disadvantages of both options. We also discuss the principal issues that must yet be resolved.


2009 ◽  
Vol 28 (1) ◽  
pp. 3-9 ◽  
Author(s):  
B. Malekynia ◽  
H. Hora ◽  
N. Azizi ◽  
M. Kouhi ◽  
M. Ghoranneviss ◽  
...  

AbstractIn contrast to the usual laser fusion scheme with spherical irradiation and very high compression and ignition of fuel, the alternative scheme with side-on ignition of uncompressed solid density of fuel (Chu) may lead to a solution by using the now available picosecond laser pulses with higher than petawatt power. A necessary condition is to use clean laser pulses with better than 108contrast ratio for suppression of relativistic self-focusing. When updating the analysis of Chu for fusion of deuterium-tritium and proton-11B, one problem is that the correct use of the stopping power of the alpha particles had to be solved. Discrepancies are evaluated in view of the stopping power at the low temperature range of the plasmas where the change of the emitted bremsstrahlung is involved.


2012 ◽  
Vol 30 (3) ◽  
pp. 459-463 ◽  
Author(s):  
M. Ghoranneviss ◽  
A. Salar Elahi ◽  
H. Hora ◽  
G.H. Miley ◽  
B. Malekynia ◽  
...  

AbstractThe new possibility of side-on laser ignition of p-11B with negligible radioactivity encouraged to study the fusion of solid state p-7Li fuel that again turns out to be only about 10 times more difficult than the side-on ignition of solid deuterium-tritium using petawatt-picosecond laser pulses at anomalous interaction conditions if very high contrast ratio. Updated cross sections of the nuclear reaction are included.


1992 ◽  
Vol 10 (1) ◽  
pp. 145-154 ◽  
Author(s):  
P. Pieruschka ◽  
L. Cicchitelli ◽  
R. Khoda-Bakhsh ◽  
E. Kuhn ◽  
G. H. Miley ◽  
...  

Since DT laser fusion with 10-MJ laser pulses for 1000-MJ output now offers the physics solution for an economical fusion energy reactor, the conditions are evaluated assuming that controlled ICF reactions will become possible in the future using clean nuclear fusion fuel such as deuterium-helium(3) or hydrogen-boron(11). Using the transparent physics mechanisms of volume ignition of the fuel capsules, we show that the volume ignition for strong reduction of the optimum initial temperature can be reached for both types of fuels if a compression about 100 times higher than those in present-day laser compression experiments is attained in the future. Helium(3) laser-pulse energies are then in the same range as for DT, but ten times higher energies will be required for hydrogenboron(11).


2001 ◽  
Author(s):  
Victor N. Chernov ◽  
Alexander V. Charukchev ◽  
Roman F. Kurunov ◽  
Vladimir A. Malinov ◽  
Nikolai V. Nikitin ◽  
...  

Author(s):  
Haitian Wang ◽  
Ge Li ◽  
Shijun Qin

The ITER is an international collaborative project aimed at demonstrating the scientific and technological feasibility of fusion energy for peaceful purposes. China as one of the seven parties takes part in the ITER, and wishes to grasp the remote handling technology, which is one of the four key technologies related to the future fusion reactors for electric power generation. The transfer cask system (TCS) is one subsystem of ITER remote handling system, which provides the means for the remote transfer of (clean/activated/contaminated) in-vessel components and Remote Handling Equipment between Hot Cell Facility and Vacuum Vessel through dedicated galleries and lift in the ITER buildings. The TCS can work in the nuclear radiation environment and can be fully driven by self powered electricity with high energy density batteries. Its driving force is provided by nearly twenty servo motors. The remote handling technology can lay the foundation for developing demonstration nuclear fusion power plant in China on self-reliance. Due to the gamma irradiation and the hazard material in these ITER parts, all required maintenance of the port plug and the inner components are being carried out by the TCS, which offers confinement boundaries to these components. The ITER Tokamak building includes three floors, including upper port level, equatorial port level and lower port level, linked by a lift. Due to limited Tokamak building space which is frozen and can not be changed presently, the TCS penetrates its cable tray for about 300 mm. According to the configuration each port level and the mass of the corresponding plug, the dimensions of the TCS envelope in three levels are different. The basic components and the basic parameters of the TCS are presented. Furthermore, according to each port level configuration and the safety requirement of the TCS, the radius of the curvature with the TCS trajectory is optimized, and a trajectory of each port level is determined by the positioned guidance beacons. At last, the results of the computer aided design (CAD) shows that the present conflict between TCS and Tokamak building can be designed compatible with the proposed variable structure cable tray in the ITER Tokamak building and the TCS based on a fleet of server motor driven system.


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