[en] Physicists and engineers at Princeton University's Tokamak Fusion Test Reactor (TFTR) have pushed the machine beyond its design specifications to set a new record for fusion energy output. Even better, the fusion machine is running more smoothly than ever. A hot magnetically confined plasma in TFTR produced 10.7 megawatts of fusion power in this experiment. Further description is given in this paper

[en] The problem considered is the feasibility of unconventional - other than Tokamak - fusion methods: driven plasma and DD or p + B¹¹ → 3 He⁴ reactions. A necessary condition is that the energy loss rate from the injected ion beam to the plasma should be smaller than the power generated. In the introduction the energy loss mechanism are enumerated Part I is concerned with the derivation and solution of a Boltzmann equation appropriate to the problem. At the end of this part the reasons are discussed why the attempt at the solution failed. Apparently because of lack of time this sophisticated method is abandoned and simpler methods are used in Part II. An estimation of the energy transfer rate is made and a result identical to that of Glasstone-Lovberg is obtained. A parametrical study with emphasis of the He³ semicatalysed DD reaction is undertaken. One conclusion is that the assumption of Tsub(e) = 1/10 Tsub(i) gives only for the latter reaction a power ratio of 0724 < 1 at Tsub(i) = 1000keV and Tsub(e) = 100keV. The other conclusion is that kTsub(i) approximately kTsub(e) should be fulfilled (i.e. thermal equilibrium) in order that the energy taken away by the ions disappearing through the loss cone should be smaller than the fusion energy generated. (G.Q.)

[en] Published in summary form only

No abstract available

[en] In this paper, a comprehensive model is developed to study alpha-heating in inertially confined plasmas. It describes the time evolution of a central low-density hot spot confined by a compressible shell, heated by fusion alphas, and cooled by radiation and thermal losses. The model includes the deceleration, stagnation, and burn phases of inertial confinement fusion implosions, and is valid for sub-ignited targets with ≤10× amplification of the fusion yield from alpha-heating. The results of radiation-hydrodynamic simulations are used to derive realistic initial conditions and dimensionless parameters for the model. It is found that most of the alpha energy (~90%) produced before bang time is deposited within the hot spot mass, while a small fraction (~10%) drives mass ablation off the inner shell surface and its energy is recycled back into the hot spot. Of the bremsstrahlung radiation emission, ~40% is deposited in the hot spot, ~40% is recycled back in the hot spot by ablation off the shell, and ~20% leaves the hot spot. We show here that the hot spot, shocked shell, and outer shell trajectories from this analytical model are in good agreement with simulations. Finally, a detailed discussion of the effect of alpha-heating on the hydrodynamics is also presented.

[en] Lithium oxide is one of the candidate tritium breeders for a fusion reactor. A computational survey, using experimentally measured activity coefficients for LiOH in Li₂O, was made of the thermodynamic behavior of Li₂O as a fusion reactor breeder blanket material. All significant species in establishing an equilibrium state, including those generated from the effects of H-T exchange, are included in the analysis. Oxygen activity is a variable that was found to strongly influence the balance of the molar quantities and activities of various species. These relationships are important in assessing the HT-HTO balance in the gas phase, the enhancement of tritium release by protium purging, the vaporization of LiOH/LiOT and Li, and the effects of elemental lithium and LiT in the condensed phase. (orig./RK)

[en] Much has been learned about muon-catalyzed fusion since the last conference on emerging nuclear energy systems. Here the authors consider what they have learned about enhancing the muon-catalyzed fusion energy yield

No abstract available

No abstract available

[en] Abstract only