Inertial Confinement Fusion by Light Ion Beam

Author(s):  
S. Miyamoto ◽  
T. Ozaki ◽  
A. Yoshinouch ◽  
S. Higaki ◽  
K. Imasaki ◽  
...  
1994 ◽  
Vol 12 (2) ◽  
pp. 283-324 ◽  
Author(s):  
J.P. Quintenz ◽  
D.B. Seidel ◽  
M.L. Kiefer ◽  
T.D. Pointon ◽  
R.S. Coats ◽  
...  

The computational tools used in the investigation of light-ion diode physics at Sandia National Laboratories are described. Applied-B ion diodes are used to generate intense beams of ions and focus these beams onto targets as part of Sandia's inertial confinement fusion program. Computer codes are used to simulate the energy storage and pulse forming sections of the accelerator and the power flow and coupling into the diode where the ion beam is generated. Other codes are used to calculate the applied magnetic field diffusion in the diode region, the electromagnetic fluctuations in the anode-cathode gap, the subsequent beam divergence, the beam propagation, and response of various beam diagnostics. These codes are described and some typical results are shown.


2004 ◽  
Vol 124 (1) ◽  
pp. 85-90 ◽  
Author(s):  
Tetsuo Someya ◽  
Aleksandar Ogoyski ◽  
Shigeo Kawata ◽  
Toru Sasaki

2006 ◽  
Vol 24 (3) ◽  
pp. 359-369 ◽  
Author(s):  
TETSUO SOMEYA ◽  
KENTAROU MIYAZAWA ◽  
TAKASHI KIKUCHI ◽  
SHIGEO KAWATA

In order to realize an effective implosion, the beam illumination non-uniformity and implosion non-uniformity must be suppressed to less than a few percent. In this paper, a direct-indirect mixture implosion mode is proposed and discussed in heavy ion beam (HIB) inertial confinement fusion (HIF) in order to release sufficient fusion energy in a robust manner. On the other hand, the HIB illumination non-uniformity depends strongly on a target displacement (dz) in a reactor. In a direct-driven implosion mode dz of ∼20 μm was tolerance and in an indirect-implosion mode dz of ∼100 μm was allowable. In the direct-indirect mixture mode target, a low-density foam layer is inserted, and radiation is confined in the foam layer. In the foam layer the radiation transport is expected in the lateral direction for the HIB illumination non-uniformity smoothing. Two-dimensional implosion simulations are performed and show that the HIB illumination non-uniformity is well smoothed. The simulation results present that a large pellet displacement of ∼300 μm is tolerable in order to obtain sufficient fusion energy in HIF.


2013 ◽  
Vol 19 (4) ◽  
pp. 1073-1079 ◽  
Author(s):  
Yongqiang Li ◽  
Xue Liu ◽  
Xinyi Li ◽  
Yiyang Liu ◽  
Yi Zheng ◽  
...  

AbstractQuality control of the inertial confinement fusion (ICF) target in the laser fusion program is vital to ensure that energy deposition from the lasers results in uniform compression and minimization of Rayleigh–Taylor instabilities. The technique of nuclear microscopy with ion beam analysis is a powerful method to provide characterization of ICF targets. Distribution of elements, depth profile, and density image of ICF targets can be identified by particle-induced X-ray emission, Rutherford backscattering spectrometry, and scanning transmission ion microscopy. We present examples of ICF target characterization by nuclear microscopy at Fudan University in order to demonstrate their potential impact in assessing target fabrication processes.


2017 ◽  
Vol 32 (04) ◽  
pp. 1750016 ◽  
Author(s):  
R. Azadifar ◽  
M. Mahdavi

In ion fast ignition (FI) inertial confinement fusion (ICF), a laser accelerated ion beam called igniter provides energy required for ignition of a fuel pellet. The laser accelerated deuteron beam is considered as igniter. The deuteron beam with Maxwellian energy distribution produced at the distance d = 500 [Formula: see text]m, from fuel surface, travels during time t = 20 ps and arrives with power [Formula: see text] to the fuel surface. Then, the deuteron beam deposits its energy into fuel by Coulomb and nuclear interactions with background plasma particles during time t = 10 ps, with power [Formula: see text]. Since time and power of the two stages have same order, to calculate the total power deposited by igniter beam, both stages must be considered simultaneously. In this paper, the exact power of each stage has been calculated separately, and the total power [Formula: see text] has been obtained. The obtained results show that the total power deposition [Formula: see text] is significantly reduced due to reducing different temperature between projectile and target particles.


1988 ◽  
Vol 57 (7) ◽  
pp. 2233-2236
Author(s):  
Kazuo Imasaki ◽  
Shuji Miyamoto ◽  
Tatsuro Akiba ◽  
Sadao Nakai ◽  
Chiyoe Yamanaka

1997 ◽  
Vol 15 (3) ◽  
pp. 461-470 ◽  
Author(s):  
R.E. Olson ◽  
J.J. Macfarlane

Light ion beam inertial confinement fusion (ICF) is a concept in which intense beams of low atomic number ions would be used to drive ICF targets to ignition and gain. Here, results from numerical simulations are presented describing the operation of an indirect-drive light-ion ICF target designed for a commercial power plant application. The simulations indicate that the ICF target, consisting of an X-ray-driven capsule embedded in a spherical foam-filled hohlraum, will produce a fusion energy output of over 500 MJ when driven with lithium ion beams containing a total input energy of 8 MJ.


1981 ◽  
Vol 50 (9) ◽  
pp. 3085-3090 ◽  
Author(s):  
Jun-yoshi Okehara ◽  
Shunji Ido ◽  
Katsunobu Nishihara ◽  
Chiyoe Yamanaka

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