HTGR Knowledge Base

Conference Article: Safety-related experiences with the AVR reactor

Krueger, K.J.; Ivens, G.P. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Duesseldorf (Germany, F.R.))

Abstract

The 15 MW nuclear power station of the AVR is in operation since 1967. The operational results have clearly demonstrated its high safety potential. The fuel elements have shown good retention properties for fission products which lead to a low activity in the coolant gas, on the primary circuit surfaces and the deposited graphite dust. As a result the activity release into the atmosphere is low. The calculated maximum dose in the surrounding of the plant is less that 1 mrem/year. In case of a loss of coolant accident the activity inventory of the coolant would flow into the containment but would not reach the environment. But even if the activity would be released the maximum radiation dose in the environment would be negligible.

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key words: avr reactor; coolants; fission product release; leaks; loss of coolant; radiation doses; reactor operation; reactor operators; reactor safety experiments; specifications; accidents; enriched uranium reactors; gas cooled reactors; graphite moderated reactors; helium cooled reactors; homogeneous reactors; htgr type reactors; operation; pebble bed reactors; power reactors; reactor accidents; reactors; solid homogeneous reactors; thermal reactors; thorium reactors
Reference:
Specialists' meeting on safety and accident analysis for gas-cooled reactors. Oak Ridge, TN (USA). 13-15 May 1985
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--358, pp:61-70