Abstract
This paper addresses the problem of design faults for nuclear power stations with fast reactors, mainly the clogging of the cross section of an individual fuel element, caused by swelling of the element itself, by precipitation of foreign substances from the coolant or by penetration by foreign objects. This leads to a reduction in the flow of coolant through the element and damage, destruction or melting of the fuel element with consequential damage to its immediate surroundings. This paper examines some aspects of such a worst-case fault for reactor type BN-600. The development of the fault is observed at the stages of fuel-element overheating and the failure of its seal by observing the delayed neutrons. If the reactor has not already been shut down, the boiling of the sodium and the melting of the fuel can be registered from the neutron-flux and acoustic noise and also by the system for monitoring the reactivity balance, which initiates an alarm signal.
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