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Inertial-confinement fusion central-station electric-power-generating plant. Final report, March 1, 1979-September 30, 1980. Volume 2

Technical Report ·
DOI:https://doi.org/10.2172/6377604· OSTI ID:6377604
This report contains a complete description of the subsystems of the power plant including driver, driver power supply, pellet fabrication, pellet injection and aiming, data handling and control, evacuation, tritium and radwaste handling, first wall protection, first wall and structure, heat removal, tritium breeding and neutron shielding, maintenance and repair and balance of plant. In addition, it contains analytic support for the conceptual designs developed for each subsystem. The emphasis of the effort was on designing a viable reactor cavity and on solving the problems of interfacing the driver systems with the reactor cavity. The reactors generate 3500 NWt by irradiating a pellet whose gain is 175 from two opposite sides with a total of 2 MJ driver energy at a 10 Hz repetition rate. Because the nominal laser driver efficiency is 10% and that for the heavy ion driver is 30%, the net electric power outputs are 1207 MWe and 1346 MWe; the net plant conversion efficiencies are 28.1% and 31.3%; and the recirculating fractions are 22.9% and 14.0% respectively. The increased power output is, however, only one of the factors considered by utilities in performing a cost minimization analysis of competing power sources for system expansion. These other factors include: capital costs, cost of construction time, operating costs, environmental and licensing costs and reliability cost.
Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
Sponsoring Organization:
USDOE
DOE Contract Number:
AC08-79DP40086
OSTI ID:
6377604
Report Number(s):
DOE/DP/40086-1(Vol.2); ON: DE81024494
Country of Publication:
United States
Language:
English