Gas-cooled high temperature nuclear reactors

Details Gas-cooled high temperature nuclear reactors Gas-cooled high temperature nuclear reactors

1978-04-25

1981-01-06

Engle, Samuel W.

176 58PB, 176 60, G21C 900

Patent

active

042434874

ABSTRACT:
A gas-cooled, and preferably helium cooled, graphite-moderated high temperature nuclear reactor of the kind having a pressure vessel containing a reactor core with fuel elements, graphite components and a primary coolant gas circuit including a steam generator and coolant gas blowers, has the steam generator disposed outside the pressure vessel and the steam generator includes a heat exchanger at least a portion of which is located above the level of the reactor core. This situation of the heat exchanger ensures that when the reactor is shut down, either intentionally or owing to a fault, a natural convection flow takes place through the coolant gas circuit and this natural convection flow is in the same direction as it is when the blowers are functioning so that the flow conducts away the decay heat from the core to the steam generator in the same way as when the blowers are in operation.

REFERENCES:
patent: 2132757 (1938-10-01), Paulson
patent: 2929768 (1960-03-01), Mahlmeister et al.
patent: 3127322 (1964-03-01), Podd
patent: 3410752 (1968-11-01), Dell
patent: 3470066 (1969-09-01), Livsey et al.
patent: 3544425 (1970-12-01), Shaw et al.
patent: 3775248 (1973-11-01), Charcharos
patent: 3998057 (1976-12-01), Haferkamp et al.

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