scholarly journals New results obtained with sulphur and bromine ions interacting with a Z-pinch hydrogen discharge

1990 ◽  
Vol 8 (4) ◽  
pp. 575-581 ◽  
Author(s):  
D. Gardes ◽  
R. Bimbot ◽  
M. F. Rivet ◽  
A. Servajean ◽  
A. Fleurier ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Essential Role ◽  
Ion Beam ◽  
Plasma Discharge ◽  
Inertial Confinement ◽  
Hydrogen Discharge ◽  
Confinement Fusion ◽  
Residual Gas ◽  
Effective Charges ◽  
Z Pinch

The experimental setup developed at Orsay for studying ion beam-plasma interactions of relevance to inertial confinement fusion has been significantly improved. In this connection, the fast valves displayed on both sides of the plasma discharge play an essential role. The amount of residual gas is then reduced by a factor of 3. New and accurate results for the stopping and the effective charges of S7+ and Br6+ in the MeV/u energy range are presented.

scholarly journals Simulation codes for light-ion diode modeling

1994 ◽  
Vol 12 (2) ◽  
pp. 283-324 ◽  
Author(s):  
J.P. Quintenz ◽  
D.B. Seidel ◽  
M.L. Kiefer ◽  
T.D. Pointon ◽  
R.S. Coats ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Power Flow ◽  
Ion Beam ◽  
Inertial Confinement ◽  
Beam Diagnostics ◽  
Computational Tools ◽  
Field Diffusion ◽  
Confinement Fusion ◽  
Computer Codes ◽  
Inertial Confinement Fusion Program

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.

scholarly journals Development and characterization of a Z-pinch-driven hohlraum high-yield inertial confinement fusion target concept

2001 ◽  
Vol 8 (5) ◽  
pp. 2257-2267 ◽  
Author(s):  
Michael E. Cuneo ◽  
Roger A. Vesey ◽  
John L. Porter ◽  
Gordon A. Chandler ◽  
David L. Fehl ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
High Yield ◽  
Inertial Confinement ◽  
Target Concept ◽  
Confinement Fusion ◽  
Fusion Target ◽  
Z Pinch ◽  
Inertial Confinement Fusion Target

scholarly journals Heavy Ion Beam Illumination Uniformity in Heavy Ion Beam Inertial Confinement Fusion

2004 ◽  
Vol 124 (1) ◽  
pp. 85-90 ◽  
Author(s):  
Tetsuo Someya ◽  
Aleksandar Ogoyski ◽  
Shigeo Kawata ◽  
Toru Sasaki
Keyword(s):  
Inertial Confinement Fusion ◽  
Ion Beam ◽  
Heavy Ion ◽  
Inertial Confinement ◽  
Confinement Fusion ◽  
Heavy Ion Beam

scholarly journals Experimental investigation of Z-pinch radiation source for indirect drive inertial confinement fusion

2019 ◽  
Vol 4 (4) ◽  
pp. 046201 ◽  
Author(s):  
Zhenghong Li ◽  
Zhen Wang ◽  
Rongkun Xu ◽  
Jianlun Yang ◽  
Fan Ye ◽  
...  
Keyword(s):  
Experimental Investigation ◽  
Radiation Source ◽  
Inertial Confinement Fusion ◽  
Inertial Confinement ◽  
Confinement Fusion ◽  
Indirect Drive ◽  
Z Pinch

scholarly journals Direct-indirect mixture implosion in heavy ion fusion

2006 ◽  
Vol 24 (3) ◽  
pp. 359-369 ◽  
Author(s):  
TETSUO SOMEYA ◽  
KENTAROU MIYAZAWA ◽  
TAKASHI KIKUCHI ◽  
SHIGEO KAWATA
Keyword(s):  
Inertial Confinement Fusion ◽  
Radiation Transport ◽  
Ion Beam ◽  
Fusion Energy ◽  
Heavy Ion ◽  
Inertial Confinement ◽  
Foam Layer ◽  
Lateral Direction ◽  
Confinement Fusion ◽  
Heavy Ion Fusion

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.

Characterization of Inertial Confinement Fusion (ICF) Targets Using PIXE, RBS, and STIM Analysis

2013 ◽  
Vol 19 (4) ◽  
pp. 1073-1079 ◽  
Author(s):  
Yongqiang Li ◽  
Xue Liu ◽  
Xinyi Li ◽  
Yiyang Liu ◽  
Yi Zheng ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Rutherford Backscattering Spectrometry ◽  
Ion Beam ◽  
Laser Fusion ◽  
Inertial Confinement ◽  
Uniform Compression ◽  
Nuclear Microscopy ◽  
Confinement Fusion ◽  
Icf Target

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.

scholarly journals Laser targets compensate for limitations in inertial confinement fusion drivers

2005 ◽  
Vol 23 (4) ◽  
pp. 475-482 ◽  
Author(s):  
J.D. KILKENNY ◽  
N.B. ALEXANDER ◽  
A. NIKROO ◽  
D.A. STEINMAN ◽  
A. NOBILE ◽  
...  
Keyword(s):  
Inertial Confinement Fusion ◽  
Three Dimensional ◽  
Inertial Confinement ◽  
Single Shot ◽  
Fabrication Technology ◽  
Nano Material ◽  
Confinement Fusion ◽  
Computer Codes ◽  
Material Fabrication ◽  
Z Pinch

Success in inertial confinement fusion (ICF) requires sophisticated, characterized targets. The increasing fidelity of three-dimensional (3D), radiation hydrodynamic computer codes has made it possible to design targets for ICF which can compensate for limitations in the existing single shot laser and Z pinch ICF drivers. Developments in ICF target fabrication technology allow more esoteric target designs to be fabricated. At present, requirements require new deterministic nano-material fabrication on micro scale.

Power deposition of deuteron beam in fast ignition

2017 ◽  
Vol 32 (04) ◽  
pp. 1750016 ◽  
Author(s):  
R. Azadifar ◽  
M. Mahdavi
Keyword(s):  
Inertial Confinement Fusion ◽  
Ion Beam ◽  
Deuteron Beam ◽  
Fast Ignition ◽  
Total Power ◽  
Fuel Pellet ◽  
Inertial Confinement ◽  
Fuel Surface ◽  
Power Deposition ◽  
Confinement Fusion

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.

Sign in / Sign up

Export Citation Format

Share Document