[en] The FRX device at Los Alamos is a long reversed field theta pinch, a special form of compact torus. Using the conventional formalism of 1 1/2 D equilibria to disucss the problem, we find some novel features. Computations have verified what intuition tells us about the FRX: because of its great aspect ratio, there exists a region of the device for which a simple 1D (cylindrical) treatment is appropriate

[en] Transport and radiation studies are performed for 2:1 ratio elliptical cross-section plasmas, using the toroidal geometry diffusion code G2M. The Torus I and II machines at Columbia are used as models. From the viewpoint of radiation, these machines represent the general classes of cold pinch-tokamaks (T approx. 10 eV) and hot pinch-tokamaks (T approx. 100 eV), which are qualitatively different because of oxygen impurities. Two types of profiles are studied: parabolic density and temperature distributions, and force-free current profiles, with density peaked near the center and temperature almost flat

[en] Separate abstracts were prepared for each of the 20 included appendices

[en] DDRFP is a 1-1/2 dimensional plasma transport code, based on the G2M tokamak code but extended to handle RFPs. The code treats a plasma of ions and electrons whose density and temperature vary across flux surfaces and with time, coupled to a magnetic field. As in G2M, plasma and field are assumed to evolve through a succession of states of pressure balance, and parallel transport is assumed fast enough to keep temperature and density almost constant on flux surfaces. The independent variables are the volume V (per radian) of a flux surface and the time t. Cgs units are used throughout. The primary dependent variables of the code are the electron density n(V,t), the electron pressure P/sub e/(V,t), the ion pressure P/sub i/(V,t), the poloidal flux psi (V,t), and the poloidal current (times 4π/c)f(V,t). We thus need five partial differential equations to advance these five functions. In addition, there are models for subsidiary quantities such as fluxes, ionization states, and neutral densities. These are given in terms of the primary dependent variables

[en] An abstract was prepared for the progress summary on transport theory for open and closed magnetic configurations. Seven abstracts were prepared for included appendices of more detailed work on individual devices. Also included is a list of publications, technical presentations, and DOE program contributions

[en] The purpose of this note is to set down the Pfirsch-Schlueter and classical transport coefficients used in G2M. The argument used is due to Hazeltine and Hinton (Phys. Fluids, 16:1833(1973)), and the results of course agree with theirs

[en] We are developing a series of computer codes (MAK0, MAK1, MAK2) which realistically model the performance of tokamak reactors in 0, 1, and 2 dimensions. Versions of MAK0 and MAK1 are operational and described in this report. They solve the time evolution of the density and energy conservation equations in D-T plasmas with alphas, neutrals, and two impurity species. MAK1 solves the plasma equilibrium equation on the Lagrangian flux-coordinate grid with transport coefficients computed as surface average quantities which include Pfirsh--Schulter, neoclassical, and trapped particle effects. Plasma recycle and impurity injection are self-consistent with charged particle and neutron outflow. An average ion coronal model determines impurity charges. Major radius control and plasma scrapeoff by a limiter are modeled. These codes are applicable to a wide variety of physics or engineering studies of tokamak reactors

[en] Because of the unique magnetic topology associated with the Reversed-Field Pinch (RFP), the compact reactor embodiment for this approach is particularly attractive from the viewpoint of low-field resistive coils operating with Ohmic losses that can be made small relative to the fusion power. The cost-optimized Compact RFP Reactor (CRFPR) design would operate with fusion-power-core power densities and mass utilizations that are comparable to fission power plants and are an order of magnitude more favorable than the conventional fusion approaches. A comprehensive system model predicts the CRFPR point design to be surprisingly resilient to changes in key, but relatively unknown, physics and systems parameters

[en] A linearization technique was used to describe a set of equations that modeled tokamak transport. This technique has allowed the equations to be solved using implicit (time) differencing while retaining their conservation properties and subject to the elliptic constraint

[en] The purpose of this work is to attempt a ID numerical simulation of the start up phase of ZT-40, starting from the post-implosion time. We being with a cold low density plasma with modest toroidal embedded field, since we are prohibited from calculating the breakdown, due to code shortcomings. We aim to calculate plasma buildup and heating, and evolution of both components of field and current to a final state