System and method for controlling operation of boiling water rea

Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component

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376210, 376379, 376214, G21C 732

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active

044003439

ABSTRACT:
The pressure P.sub.R in the reactor pressure vessel, the flow rate W.sub.c of the cooling water flowing through the core in the reactor pressure vessel, and the flow rate W.sub.STM of the steam supplied from the reactor pressure vessel to the turbine are detected. The enthalpy H.sub.f of the saturated cooling water is determined on the basis of the pressure P.sub.R. The values of the cooling water flow rate W.sub.c, the steam flow rate W.sub.STM, the enthalpy H.sub.f of the saturated cooling water and a predetermined enthalpy H.sub.IN of the cooling water at the core inlet are substituted into the equation below thereby to obtain the enthalpy H.sub.fw of the feed water. ##EQU1## An error is determined between the feed-water enthalpy H.sub.fw thus obtained and the enthalpy T.sub.fw of the feed water actually supplied into the reactor pressure vessel, and on the basis of this error, the opening of the flow rate control valve on the turbine bleeding pipe is adjusted, so that the flow rate of the steam bled from the turbine for heating the feed water is adjusted according to the error.

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A Design Description of Dresden Nuclear Power Station, (11/26/56), pp. 1-25.

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