Monitoring method and monitoring program for boiling water...

Induced nuclear reactions: processes – systems – and elements – With control of reactor – Power output control

Reexamination Certificate

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C376S298000, C376S207000, C376S361000

Reexamination Certificate

active

08009788

ABSTRACT:
A boiling water reactor includes a reactor pressure vessel; a steam pipe for transporting steam generated in the reactor pressure vessel out from a steam dome positioned at an upper part of the reactor pressure vessel; a high pressure turbine connected to the steam pipe and driven by the steam; a feedwater heater which heats feedwater supplied to the reactor pressure vessel using bleed steam flowing from the high pressure turbine to the feedwater heater; a bleeding valve which adjusts a flow rate of the bleed steam; and a pressure sensor provided in a main steam line including the steam dome and the steam pipe. The boiling water reactor further includes a monitor and control system which controls an opening degree of the bleeding valve based on a magnitude of fluctuating pressure in the main steam line that is detected by the pressure sensor.

REFERENCES:
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patent: 4879087 (1989-11-01), Akiyama et al.
patent: 6198786 (2001-03-01), Carroll et al.
patent: 2006/0078081 (2006-04-01), Bilanin et al.
patent: 2007-155361 (2007-06-01), None
Anan'ev et al., “Special Features of Nuclear Power Stations in Energy Generation”, Atomnaya Energiya, vol. 28, No. 4, Apr. 1970, pp. 291-294 (English language translation enclosed).
NRC Special Inspection Report, 50-265/03-11.
Journal of Engineering for Gas Turbines and Power, Apr. 2004, vol. 126 p. 271-275.
Office Action in JP2006-051765, dated Aug. 25, 2009 (in Japanese) (2 pages).

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