DESIGN STUDIES OF A MOLTEN-SALT REACTOR DEMONSTRATION PLANT.

The MSDR, a 350-MW(e) Molten-Salt Reactor Demonstration Reactor, i s based on technology much of which was demons t ra ted by the MSRE. 26 f't high) houses a matrix of graphite slabs forming salt passages having 8 volume fraction i n the core of lo$. The flow of fue l s a l t i s distributed so tha t the temperature r i s e along any pa th : i s the same from 1050 t o 1250'F. In the primary exchanger, heat i s transferred t o barren car r ie r s a l t ( in g t WOOF, out a t l lW°F) , changer, heat i s transferred t o a stream of Hitec s a l t ( in a t 800"F, out a t 1000'F). t r i t i a t e d water which i s removed and disposed o f , Hitec generates steam a t WOOF, 2400 p s i i n a boi ler , superheater, and reheater. E lec t r ic i ty i s produced a t an overall efficiency of 36.e. Soluble f iss ion products are removed by discarding the car r ie r s a l t every 8 years a f t e r recovery of the, uranium by fluorinat$on. Volati le f i ss ion products a re removed by sparging the fue l s a l t with helium bubbles i n the reactor primary system. The fue l cycle cost was estimated t o 0.7 mill/kWhr fo r inventory, 0.3 mill/kWhr Tor replacement, and 0 .I mill/kWhr for processing, giving a t o t a l of 1.1 mills/kWhr. The cylindrical vessel (26 f t diam by In the secondary exThe Hitec oxidizes tritium t o The The purpose o f t h i s study was t o describe a semi-commercial-scale molten-salt reactor and power p l much of which was demonstrated by the Molten-Salt Reactor Experiment. The p laa t was desagned t o produce 350 electriaalmegawatts. The nuclear conversion r a t i o i s about O,9, and the specif ic power i s about 0.5 MW(e) per kilogram fissile. t h a t would be based on the technology, The reactor consists of a cyl indrical vessel about 26 f t i n diameter and about 26 f t high f i l l e d w i t h a matrix of graphite slabs forming f l o w passages 0.142 in . thick by 9-3/8 in . wide and with a volume fract ion i n i i