Global economics/energy/environmental (E{sup 3}) modeling of long-term nuclear energy futures

A global energy, economics, environment (E{sup 3}) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Using this model, consistent nuclear energy scenarios are constructed. A spectrum of future is examined at two levels in a hierarchy of scenario attributes in which drivers are either external or internal to nuclear energy. Impacts of a range of nuclear fuel-cycle scenarios are reflected back to the higher-level scenario attributes. An emphasis is placed on nuclear materials inventories (in magnitude, location, and form) and their contribution to the long-term sustainability of nuclear energy and the future competitiveness of both conventional and advanced nuclear reactors

Statistically based quarterly earnings expectation models for nonseasonal firms

Nonseasonal quarterly earnings, ARIMA models, Random walk model, Analyst coverage, C22,

Systems study of tokamak fusion--fission reactors

This publication reports the results of a two to three year effort at a systematic analysis of a wide variety of tokamak-driven fissioning blanket reactors, i.e., fusion--fission hybrids. It addresses the quantitative problems of determining the economically most desirable mix of the two products: electric power and fissionable fuel and shows how the price of electric power can be minimized when subject to a variety of constraints. An attempt has been made to avoid restricting assumptions, and the result is an optimizing algorithm that operates in a six-dimensional parameter space. Comparisons are made on sets of as many as 100,000 distinct machine models, and the principal results of the study have been derived from the examination of several hundred thousand possible reactor configurations

MHD equilibrium and stability considerations for high-aspect-ratio ARIES-I tokamak reactors

The requirements of an external poloidal field coil (PFC) system with minimum stored energy, double-null divertor plasmas with elongated D shape, adequate passive stabilization of plasma vertical displacement by a vacuum vessel located behind the blanket zone, and an enhanced plasma beta limit in the first stability regime are incorporated in the ARIES-I concept for a high-field tokamak reactor with high aspect ratio (A = 4.5). The plasma current and pressure profiles are also made consistent with enhanced bootstrap current I{sub bs} and reduced current drive power by means of ion cyclotron wave (ICW) or neutral beam (NB) injection. These lead to plasmas characterized by an elongation k{sub x} of 1.8 to the divertor X-point, a triangularity {delta}{sub x} of 0.7, a safety factor q on axis of q{sub 0} {approx} 1.5, a safety factor at the edge q{sub 95} > 4, a plasma beta {beta} {approx} 2%, and a poloidal beta given by {epsilon}{beta}{sub p} {approx} 0.5 ({epsilon} = 1/A). With a plasma current I{sub p} of 11 MA, a toroidal field B{sub t} of 13 T at the major radius R{sub 0} of 6.5 m, and over 3.5 m of clearance between the PFCs and the plasma edge, the stored energy in the PFC system ranges from 20 GJ during plasma operation at low beta to 12 GJ during plasma operation at high beta. 16 refs., 6 figs., 2 tabs