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Using the shield for thermal energy storage in pulsar

Authors :
Farrokh Najmabadi
G. T. Sager
C.P.C. Wong
Edward T. Cheng
M.Z. Hasan
Laila El-Guebaly
C. Brimer
I.N. Sviatoslavski
Lester M. Waganer
James Blanchard
D.K. Sze
Shahram Sharafat
Charles G. Bathke
Source :
Fusion Engineering and Design. 29:43-50
Publication Year :
1995
Publisher :
Elsevier BV, 1995.

Abstract

The PULSAR pulsed tokamak power plant design utilizes the outboard shield for thermal energy storage to maintain full 1000 MW(e) output during the dwell period of 200 s. Thermal energy resulting from direct nuclear heating is accumulated in the shield during the 7200 s fusion power production phase. The maximum shield temperature may be much higher than that for the blanket because radiation damage is significantly reduced. During the dwell period, thermal power discharged from the shield and coolant temperature are simultaneously regulated by controlling the coolant mass flow rate at the shield inlet. This is facilitated by throttled coolant bypass. Design concepts using helium and lithium coolant have been developed. Two-dimensional time-dependent thermal hydraulic calculations were performed to confirm performance capabilities required of the design concepts. The results indicate that the system design and performance can accommodate uncertainties in material limits or the length of the dwell period.

Details

ISSN :
09203796
Volume :
29
Database :
OpenAIRE
Journal :
Fusion Engineering and Design
Accession number :
edsair.doi...........5171a792a55afedc4cc0b29ba2a0ced7
Full Text :
https://doi.org/10.1016/0920-3796(95)80004-h