[en] It is concluded that deuterium/helium-3 fusion faces a more difficult physics development path but an easier technology development path than does deuterium/tritium. Early D/He-3 tests in next generation D/T fusion experiments might provide a valuable D/He-3 proof-of-principle at modest cost. At least one high leverage alternate concept should be vigorously pursued. Space applications of D/He-3 fusion are critically important to large scale development

[en] The non-adiabatic part of the electron distribution in toroidal geometry is investigated through numerical solution of the drift kinetic equation in various parameter regions. A Lorentz operator is used to model collisions for both trapped and untrapped electrons, thus including angle scattering for all of velocity space. Both poloidal and pitch angle dependence of the electron magnetic curvature and gradient drifts are included without the necessity of bounce averaging. No special boundary conditions are used at the trapped-untrapped electron boundary. A preconditioned conjugate gradient technique is used to solve the drift kinetic equation. The result is used in a dispersion relation which includes ion inertia and ion Landau damping to find growth rates for the dissipative trapped electron mode in the radially local case. Comparisons are made to results from simpler approximations such as the Krook model. The effects of magnetic curvature and gradient drifts are examined, as is the dependence of growth rates and distribution functions on collision frequency

[en] A generic magnetic fusion rocket model is developed and used to explore the limits of fusion propulsion systems. Two fusion fuels are examined, D-T and D-(He-3), and the D-(He-3) fuel cycle is found to give a higher specific power in almost all parameter regimes. The key findings are that (1) magnetic fusion should ultimately be able to deliver specific powers of about 10 kW/kg and (2) specific powers of 15 kW/kg could be achieved with only modest extrapolations of present technology. 9 refs

[en] The tandem mirror reactor with thermal barriers has great potential for producing economic fusion power. In light of this, the present study examines the parametric dependence of important effects and seeks a preliminary set of fusion reactor design parameters. The details of the analysis are presented. A brief description is given of the numerical method involved. The parametric dependence of the equations is discussed. A set of possible reactor parameters and power flow analysis is given. Goals of central cell length of about 100 meters and Q greater than 15 were achieved

[en] This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

[en] This progress report will give a detailed breakdown of the work accomplished for ARIES-III during the contract period, November 1, 1990 to October 31, 1991. The areas of effort discussed are: Neutronics; First-Wall; Shield; Safety; Systems; Startup and Shutdown; Energy Conversion; Ripple Loss; and Fuel Resources

[en] The recently completed tandem mirror reactor study, WITAMIR-I, contains a detailed cost analysis at a reference point. Motivated by the existence of that analysis a model is developed to obtain the dependence of cost on the most important variables. Reactor parameters are varied using POWBAL, an equilibrium power balance code. Then, POWBAL output plus cost parameters are fed into the subroutine COST. The analysis is limited to configurations similar to WITAMIR-I, expanding costs about the reference point. This is a simplified model that allows for parametric studies without necessitating the detailed evaluation done for the reference design. It is useful in setting design parameters that minimize the cost of electricity as well as in analyzing the relative importance of the different parts of the plant

[en] The objectives of the University of Wisconsin effort for this contract were to: (1) participate in the Technology Development Facility (TDF) study; (2) study the effect of melt layer and coating stability on pumped limiters; and (3) participate in the FED/INTOR Cost-Risk-Benefit Study. Some details of each study are given

[en] The work performed for ''Fusion Reactor Physics and Technology Studies'' was to participate with Lawrence Livermore National Laboratory (LLNL) and others in the design of the Minimars Tandem Mirror power reactor. This design activity was a collaborative effort with LLNL being responsible for the physics and program administration. The Fusion Technology Institute (FTI) of the University of Wisconsin was responsible for nuclear technology (central cell blanket/reflector/shield design, neutronics, activation, tritium issues, and end cell shielding), and the design of the central cell magnets. In addition, FTI provided assistance to LLNL on the plasma physics modeling of the plasma halo. An interim report on the Minimars design has been issued, and a final report covering all aspects of Minimars is in press. In addition, various reports and conference papers covering aspects of the design have been issued, and are listed in this report. A summary of the FTI contribution to the Minimars design study is presented

[en] The paper discusses progress in the system design of the Tiber-II tokamak. In particular, topics discussed are neutronics analysis; thermal hydraulics analysis; activation analysis; LOCA and LOFA analysis; D/He-3 operation on Tiber-II; and a scoping design study of a D/He Tandem mirror reactor