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[4] [5] Included a large direct cycle. 5 recirculation loops, variable speed external recirculation pumps (one pump per loop, each pump's flow rate could be varied from 6,400 to 32,000 US gallons per minute (0.40 to 2.02 m 3 /s)).
Auxiliary feedwater is a backup water supply system found in pressurized water reactor nuclear power plants (PWRs). This system, sometimes known as emergency feedwater, can be used to cool the reactor, if normal feedwater to the steam generators fails to work.
If one of the two feedwater pumps fails during operation, the feedwater system will command the recirculation system to rapidly reduce core flow, effectively reducing reactor power from 100% to 50% in a few seconds. At this power level a single feedwater pump can maintain the core water level.
The first commercial APR-1400 reactors at Shin Kori were approved in September 2007, [12] with construction starting in October 2008 (Unit 3) and August 2009 (Unit 4). [3] [13] [14] Shin Kori-3 was initially scheduled to commence operation by the end of 2013, but the schedules for both Units 3 & 4 were delayed by approximately one year to replace safety-related control cabling, which had ...
Slightly different versions of the ABWR are offered by GE-Hitachi, Hitachi-GE, and Toshiba. [5]In 1997 the GE-Hitachi U.S. ABWR design was certified as a final design in final form by the U.S. Nuclear Regulatory Commission, meaning that its performance, efficiency, output, and safety have already been verified, making it bureaucratically easier to build it rather than a non-certified design.
The feed water cycle begins with condensate water being pumped out of the condenser after traveling through the steam turbines. The condensate flow rate at full load in a 500 MW plant is about 6,000 US gallons per minute (400 L/s). Diagram of boiler feed water deaerator (with vertical, domed aeration section and horizontal water storage section).
There are 1,132 fuel rod bundles and the thermal power is 4,500 MWth in the standardized SBWR. [1] The nominal output is rated at 1594 MWe gross and 1535 MWe net, yielding an overall plant Carnot efficiency of approximately 35%. [2]
Dresden 1 Nuclear Flow Diagram featured a secondary steam generator for load following. The reactor featured a dual cycle, with steam coming from both the stream drum and steam generators. This made for rapid response to changes in power demand. Reactor power was regulated by actuation of the secondary admission valve by the turbine's governor.