Author/Authors :
Mehedinteanu، نويسنده , , Stefan ، نويسنده ,
Abstract :
The pressure tube reactors, especially CANDU type, have a calandria low pressure vessel
(near to atmospheric pressure) immersed into a concrete vault ®lled with water. The accident
analysis done by ELFIN-HTCELL code for the channel heat up and by ¯uid ¯ow PHOE-
NICS code as applied for moderator cooling system ecacy, showed that even the moderator
cooling system operates, in some transients sequences where the normal heat sinks are lost,
and the top core pressure tubes can reach burst conditions, which means that the ®ssion pro-
duct secondary retaining barrier gets destroyed, and yet the core can be cooled by water
admission through the ruptured tubes from the emergency core cooling system (ECC), if it is
available. Otherwise, if in many accident sequences the moderator cooling system remains the
ultimate heat sink for the core fuel, and it is not available even from the accident start, a core
melt appears. Taking into account the ``naturalʹʹ advantage oered by the presence of both
pools in calandria and in the vault, separated by the calandria vessel, the introduction of
density locks between them could be a safety passive design solution. When the temperature
of moderator water gets higher the density lock cold-hot interface loss stability and thus the
density locks get ``openʹʹ fully permitting the admission of the cool water from the vault pool
in calandria. Therefore, by natural circulation the decay heat is transferred via an air-cooling
tower, and no mechanical moving parts are needed to open this circuit. Also, if the vault
water is borated, it can be used to stop the nuclear reaction when the normal shutdown sys-
tems are not available and a positive reactivity coecient appears, e.g. large loss of coolant
accident (LOCA)
Keywords :
Density locks , Nuclear safety , Pressure tubes reactors , CANDU , Severe accidents , Positive reactivity coe?cient , Safety passive measures