Nuclear Power Engineering
Secondary cooling circuit is a must in molten sodium cooled fast breeder reactor for

Faster heat removal rate from the core
Achieving high degree of superheat in the steam
Lowering the coolant circulation pressure
Avoiding the mixing of water with radioactive sodium, as it may cause explosion

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Nuclear Power Engineering
In a pressurised water reactor (PWR), the

Fuel is natural uranium and heavy water acts both as moderator & coolant
Use of moderator is not required
Coolant water boils in the core of the reactor
Coolant water is pressurised to prevent bulk boiling of water in the core

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