scholarly journals Recyclable transmission line (RTL) and linear transformer driver (LTD) development for Z-pinch inertial fusion energy (Z-IFE) and high yield.

2007 ◽  
Author(s):  
Robin Arthur Sharpe ◽  
Alexander S Kingsep ◽  
David Lewis Smith ◽  
Craig Lee Olson ◽  
Paul F Ottinger ◽  
...  
Keyword(s):  
Transmission Line ◽  
Fusion Energy ◽  
High Yield ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Linear Transformer Driver ◽  
Z Pinch

scholarly journals Recyclable transmission line concept for z-pinch driven inertial fusion energy.

2003 ◽  
Author(s):  
J. S. De Groot ◽  
Craig Lee Olson ◽  
Kyle Robert Cochrane ◽  
Stephen A. Slutz ◽  
Roger Alan Vesey ◽  
...  
Keyword(s):  
Transmission Line ◽  
Fusion Energy ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Z Pinch

scholarly journals Nova Upgrade Program: Ignition and beyond

1993 ◽  
Vol 11 (2) ◽  
pp. 291-298
Author(s):  
E. Storm ◽  
E.M. Campbell ◽  
W.J. Hogan ◽  
J.D. Lindl
Keyword(s):  
Inertial Confinement Fusion ◽  
Hot Spot ◽  
Fusion Energy ◽  
Coupling Efficiency ◽  
Capital Cost ◽  
Test Facility ◽  
High Yield ◽  
Target Chamber ◽  
Inertial Fusion ◽  
Inertial Fusion Energy

The Lawrence Livermore National Laboratory (LLNL) Inertial Confinement Fusion (ICF) Program is addressing the critical physics and technology issues directed toward demonstrating and exploiting ignition and propagating burn to high gain with ICF targets for both defense and civilian applications. Nova is the primary U.S. facility employed in the study of the X-ray-driven (indirect drive) approach to ICF. Nova's principal objective is to demonstrate that laser-driven hohlraums can achieve the conditions of driver-target coupling efficiency, driver irradiation symmetry, driver pulseshaping, target preheat, and hydrodynamic stability required by hot-spot ignition and fuel compression to realize a fusion gain.The LLNL ICF Program believes that the next major step in the national ICF Program is the demonstration of ignition and moderate gain (G ≤ 10). Recent theoretical and experimental results show that the ignition drive energy threshold can be reduced significantly by operating indirectly driven targets at radiation temperatures ∼ 1.3–1.6 times higher (thereby achieving higher implosion velocity) than originally proposed for the Laboratory Microfusion Facility (LMF). (Temperatures of ∼ 1.3 times higher have already been demonstrated on Nova.) Specifically, it should be possible to demonstrate ignition and propagating with burn about 1–2 MJ of laser energy as against the 5–10 MJ necessary for the high-yield LMF. LLNL proposes to upgrade the existing Nova facility to 1–2 MJ (2- to 4-ns pulses) and demonstrate ignition and propagating burn to moderate gain with appropriately scaled hydrodynamic equivalents of high-yield targets.Once moderate gain has been demonstrated at 1–2.0 MJ on the Nova Upgrade, investigations into improving, by about 50%, the coupling efficiency between the driver and the capsule could provide gains >20 at about 1 MJ or less. A database for gain below 1-MJ driver energies could lead to a low-capital-cost Engineering Test Facility (ETF) for a first inertial fusion energy engineering reactor. Because the capital cost for both the target chamber and the driver scale with size, there is the opportunity to realize large savings by lowering the required driver energy necessary to demonstrate the technology for a first demonstration power plant. A target gain, G ∼ 25, at a driver energy, ED ∼ 0.75 MJ, would be self-sustaining for a driver efficiency of ∼10% and a thermal-to-electric conversion efficiency of ∼33% and at 12 Hz would generate ∼10 MW of gross electric power. Although the cost of electricity would be high, the combination of low capital cost and early demonstration of reactor technology would be an attractive step in the development of inertial fusion energy.

A Concept for Containing Inertial Fusion Energy Pulses in a Z-Pinch-Driven Power Plant

2003 ◽  
Vol 43 (3) ◽  
pp. 447-455 ◽  
Author(s):  
Gary E. Rochau ◽  
Charles W. Morrow ◽  
Peter J. Pankuch
Keyword(s):  
Power Plant ◽  
Fusion Energy ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Z Pinch

Improvement of the Inertial Fusion Energy Reactor Performance by Means of UF4and ThF4

2003 ◽  
Vol 43 (2) ◽  
pp. 230-249 ◽  
Author(s):  
Sebahattin Ünalan ◽  
S. Orhan Akansu ◽  
Hanifi Saraç
Keyword(s):  
Fusion Energy ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Reactor Performance ◽  
Fusion Energy Reactor

scholarly journals Fusion cross-sections for inertial fusion energy

2004 ◽  
Vol 22 (4) ◽  
pp. 469-477 ◽  
Author(s):  
XING ZHONG LI ◽  
BIN LIU ◽  
SI CHEN ◽  
QING MING WEI ◽  
HEINRICH HORA
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Light Nucleus ◽  
Resonant Tunneling ◽  
Fusion Energy ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Fusion Reactions ◽  
Tunneling Model ◽  
New Formula

The application of selective resonant tunneling model is extended from d + t fusion to other light nucleus fusion reactions, such as d + d fusion and d + 3He. In contrast to traditional formulas, the new formula for the cross-section needs only a few parameters to fit the experimental data in the energy range of interest. The features of the astrophysical S-function are derived in terms of this model. The physics of resonant tunneling is discussed.

scholarly journals Status of Safety and Environmental Activities for Inertial Fusion Energy

2003 ◽  
Vol 44 (1) ◽  
pp. 34-40 ◽  
Author(s):  
J. F. Latkowski ◽  
S. Reyes ◽  
L. C. Cadwallader ◽  
J. P. Sharpe ◽  
T. D. Marshall ◽  
...  
Keyword(s):  
Fusion Energy ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Environmental Activities

Fused Silica Final Optics for Inertial Fusion Energy: Radiation Studies and System-Level Analysis

2003 ◽  
Vol 43 (4) ◽  
pp. 540-558 ◽  
Author(s):  
Jeffery F. Latkowski ◽  
Alison Kubota ◽  
Maria J. Caturla ◽  
Sham N. Dixit ◽  
Joel A. Speth ◽  
...  
Keyword(s):  
Fusion Energy ◽  
Fused Silica ◽  
System Level ◽  
Inertial Fusion ◽  
Inertial Fusion Energy ◽  
Energy Radiation ◽  
Level Analysis
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