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Alpha power channeling with two waves

Description: The complete channeling of energy from alpha particles is likely to be realized only through the excitation of a variety of waves, rather than by one wave alone. While one wave constrains more firmly the direction of the energy transfer, the necessary wave characteristics are far more easily achieved through a combination of waves, even at the expense of less restrictive motion of the {alpha}-particles.
Date: September 1, 1995
Creator: Fisch, N.J. & Herrmann, M.C.
Partner: UNT Libraries Government Documents Department

Utility of extracting {alpha}-particle energy by waves

Description: The utility of extracting {alpha}-particle power, and then diverting this power to fast fuel ions, is investigated. As power is diverted to fast ions and then to ions, a number of effects come into play, as the relative amounts of pressure taken up by electrons, fuel ions, and fast {alpha}-particles shift. In addition, if the {alpha}-particle power is diverted to fast fuel ions, there is an enhanced fusion reactivity because of the nonthermal component of the ion distribution. Some useful expressions for describing these effects are derived, and it is shown that fusion reactors with power density about twice what otherwise might be obtained can be contemplated, so long as a substantial amount of the {alpha}-particle power can be diverted. Interestingly, in this mode of operation, once the electron heat is sufficiently confined, further improvement in confinement is actually not desirable. A similar improvement in fusion power density can be obtained for advanced fuel mixtures such as D-He{sup 3}, where the power of both the energetic {alpha}-particles and the energetic protons might be diverted advantageously.
Date: May 1, 1994
Creator: Fisch, N. J. & Herrmann, M. C.
Partner: UNT Libraries Government Documents Department

A Tutorial on Alpha-channelling

Description: One of the more ambitious uses of intense microwaves in tokamaks or in other magnetic confinement deuterium-tritium (DT) fusion devices would be to divert power from energetic alpha-particles to waves. This so-called "alpha-channelling" would be a large step towards achieving economical fusion power. The intense waves, amplified by the substantial free energy in the alpha-particles, damp on fuel ions, resulting in a hot ion mode, doubling the fusion power of the reactor at the same confined pressure. If the waves damp preferentially on electrons or ions traveling in one direction, current can be driven. This tutorial explains the key concepts and recent advances that lead us to believe in the plausibility of such an effect, at the same time showing how experiments to date give us a measure of confidence in both the simulations themselves, the underlying physical assumptions, and ultimately the reasonableness of the application of these ideas to alpha-channelling in a tokamak reactor.
Date: November 1, 1998
Creator: Fisch, N.J. & Herrmann, M.C.
Partner: UNT Libraries Government Documents Department

Optimization of nonthermal fusion power consistent with energy channeling

Description: If the energy of charged fusion products can be diverted directly to fuel ions, non-Maxwellian fuel ion distributions and temperature differences between species will result. To determine the importance of these nonthermal effects, the fusion power density is optimized at constant-{beta} for nonthermal distributions that are self-consistently maintained by channeling of energy from charged fusion products. For D-T and D-{sup 3}He reactors, with 75% of charged fusion product power diverted to fuel ions, temperature differences between electrons and ions increase the reactivity by 40-70%, while non- Maxwellian fuel ion distributions and temperature differences between ionic species increase the reactivity by an additional 3-15%.
Date: February 1, 1995
Creator: Snyder, P. B.; Herrmann, M. C. & Fisch, N. J.
Partner: UNT Libraries Government Documents Department

Ignition Scaling Laws and Their Application to Capsule Design

Description: In this paper a two pronged approach is taken to investigating the energy required for ignition of inertial confinement fusion capsules. A series of one dimensional LASNEX simulations is performed to create a database of barely ignited capsules that span the parameter regime Of interest. This database is used to develop scaling laws for the ignition energy in terms of both the stagnated capsule parameters and the inflight capsule parameters, and explore the connection between these two parameter sets. The second part of this paper examines how much extra energy is required to overcome the effect of the inevitable surface imperfections that are amplified during the implosion process and can lead to capsule break up in flight or to mix of cold fuel into the hotspot, both of which can cause the capsule to fail to ignite. By means of an example, the optimization of a capsule with fixed adiibat, drive pressure, and absorbed energy is performed; the capsule that is maximally robust to these failure modes is found.
Date: October 20, 2000
Creator: Herrmann, M. C.; Tabak, M. & Lindl, J. D.
Partner: UNT Libraries Government Documents Department

Progress in Heavy Ion Target Capsule and Hohlraum Design

Description: Progress in heavy ion target design over the past few years has focused on relaxing the target requirements for the driver and for target fabrication. We have designed a plastic (CH) ablator capsule that is easier to fabricate and fill than the beryllium ablator we previously used. In addition, 2-d Rayleigh-Taylor instability calculations indicate that this capsule can tolerate ablator surface finishes up to ten times rougher than the NIF specification. We have also explored the trade-off between surface roughness and yield as a method for finding the optimum capsule. We have also designed two new hohlraums: a ''hybrid'' target and a large angle, distributed radiator target. The hybrid target allows a beam spot radius of almost 5 mm while giving gain of 55 from 6.7 MJ of beam energy in integrated Lasnex calculations. To achieve the required symmetry with the large beam spot, internal shields were used in the target to control the P2 and P4 asymmetry. The large-angle, distributed radiator target is a variation on the distributed radiator target that allows large beam entrance angles (up to 24 degrees). Integrated calculations have produced 340 MJ from 6.2 MJ of beam energy in a design that is not quite optimal. In addition, we have done a simple scaling to understand the peak ion beam power required to compress fuel for fast ignition using a short pulse laser.
Date: May 8, 2002
Creator: Callahan, D.A.; Herrmann, M.C. & Tabak, M.
Partner: UNT Libraries Government Documents Department

Enhanced loss of fast ions during mode conversion ion Bernstein wave heating in TFTR

Description: A strong interaction of fast ions with ion Bernstein waves has been observed in TFTR. It results in a large increase in the fast ion loss rate, and heats the lost particles to several MeV. The lost ions are observed at the passing/trapped boundary and appear to be either DD fusion produced tritons or accelerated D neutral beam ions. Under some conditions, enhanced loss of DT alpha particles is also seen. The losses provide experimental support for some of the elements required for alpha energy channeling.
Date: December 1, 1995
Creator: Darrow, D.S.; Majeski, R.; Fisch, N.J.; Heeter, R.F.; Herrmann, H.W.; Herrmann, M.C. et al.
Partner: UNT Libraries Government Documents Department

Enhanced loss of fusion products during mode conversion heating in TFTR

Description: Ion Bernstein waves (IBWS) have been generated by mode conversion of ion cyclotron range of frequency (ICRF) fast waves in TFTR. The loss rate of fusion products in these discharges can be large, up to 10 times the first orbit loss rate. The losses are observed at the passing/trapped boundary, indicating that passing particles are being moved onto loss orbits either by increase of their v{perpendicular} due to the wave, by outward transport in minor radius, or both. The lost particles appear to be DD fusion produced tritons heated to {approximately}1.5 times their birth energy.
Date: July 1, 1995
Creator: Darrow, D. S.; Majeski, R.; Fisch, N. J.; Heeter, R. F.; Herrmann, H. W.; Herrmann, M. C. et al.
Partner: UNT Libraries Government Documents Department

Update on specifications for NIF ignition targets and their rollup into an error budget

Description: Targets intended to produce ignition on NIF are being simulated and the simulations are used to set specifications for target fabrication. Recent design work has focused on designs that assume only 1.0 MJ of laser energy instead of the previous 1.6 MJ. To perform with less laser energy, the hohlraum has been redesigned to be more efficient than previously, and the capsules are slightly smaller. The main-line hohlraum design now has a SiO2 foam fill, a wall of U-Dy-Au, and shields mounted between the capsule and the laser entrance holes. Two capsule designs are being considered. One has a graded doped Be(Cu) ablator, and the other graded doped CH(Ge). Both can perform acceptably with recently demonstrated ice layer quality, and with recently demonstrated outer surface roughness. Smoothness of the internal interfaces may be an issue for the Be(Cu) design, and it may be necessary either to polish partially coated shells or to improve process control so that the internal layers are smoother. Complete tables of specifications are being prepared for both targets, to be completed this fiscal year. All the specifications are being rolled together into an error budget indicating adequate margin for ignition with the new designs.
Date: July 11, 2005
Creator: Haan, S W; Herrmann, M C; Amendt, P A; Callahan, D A; Dittrich, T R; Edwards, M J et al.
Partner: UNT Libraries Government Documents Department

Increasing robustness of indirect drive capsule designs against short wavelength hydrodynamic instabilities

Description: Target designs are described that are meant to achieve ignition on the National Ignition Facility. Simulations of recent indirect drive cryogenic capsule designs indicate dramatically reduced growth of short wavelength hydrodynamic instabilities, resulting from two changes in the designs. First, better optimization results from systematic mapping of the ignition target performance over the parameter space of ablator and DT-ice thickness combinations, using techniques developed by one of us (Herrmann). After the space is mapped with one-dimensional simulations, exploration of it with two-dimensional simulations quantifies the dependence of instability growth on target dimensions. Low modes and high modes grow differently in different regions of the space, allowing a trade-off of the two regimes of growth. Significant improvement in high-mode stability can be achieved, relative to previous designs, with only insignificant increase in low-mode growth. This procedure produces capsule designs that, in simulations, tolerate several times the surface roughness that could be tolerated by capsules optimized by older more heuristic techniques. Another significant reduction in instability growth, by another factor of several, is achieved with ablators with 'graded dopants.' In this type of capsule the mid-Z dopant, which is needed in the ablator to minimize x-ray preheat at the ablator-ice interface, is optimally positioned within the ablator. A fabrication scenario for graded dopants already exists, using sputter coating to fabricate the ablator shell. We describe the systematics of these advances in capsule design, discuss the basis behind their improved performance, and summarize how this is affecting our plans for NIF ignition.
Date: November 12, 2004
Creator: Haan, S W; Herrmann, M C; Dittrich, T R; Fetterman, A J; Marinak, M M; Munro, D et al.
Partner: UNT Libraries Government Documents Department