Princeton reference design fusion power plant

Conference · Wed Jan 01 04:00:00 EST 1975

OSTI ID:4093321

Price, Jr, W G

The Princeton Reference Design Fusion Power Plant is an electrical generating station based upon a large tokamak confining a D-T plasma. The plasma major and minor radii are nominally 10.5 m by 3.2 m; the toroidal field at the center-line is 6 T. With a mean ion temperature of 30 keV, an average $beta$ of 0.04, and an average tau of 3.83 s a fusion power of 3440 MW is achieved during 97 minutes of the 100 minute long-pulse cycle. The plasma throughput of 2.8 x 10$sup 22$ ions/s is deflected down a divertor channel where it cools by radiation and is neutralized, exhausting as hot gas to the vacuum pumps. The total thermal power of 5305 MW is carried by a helium coolant to a conventional steam cycle producing 2030 MW(e) net. Tritium is bred in an 80-cm thick blanket of eutectic flibe (53.1 percent beryllium fluoride and 46.9 percent lithium fluoride) with Nimonic PE-16 (43 percent nickel, 39 percent iron, 18 percent chromium) as the structural material; the blanket-averaged volume fractions are 69.8 percent flibe, 9.4 percent PE-16, and 20.8 percent helium. The breeding ratio of 1.4 will allow doubling of the 2.57 kg inventory in 121 days. The nominal wall load of 1.76 MW of DT neutrons per m$sup 2$ implies a total flux of 8.65 x 10$sup 18$n.m$sup -2$.s$sup -1$ at the wall and a corresponding helium production rate of 275 ppM/year. (auth)

• Research Organization: Princeton Univ., NJ
• NSA Number: NSA-33-014577
• OSTI ID: 4093321
• Country of Publication: IAEA
• Language: English

Related Subjects

*TOKAMAK DEVICES-- DESIGN
700200* --Fusion Energy--Fusion Power Plant Technology
BREEDING
BREEDING BLANKETS
DEUTERIUM
DIVERTORS
FLIBE
N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
TRITIUM