发明名称 CORE FLOW MEASURING OPERATION METHOD OF ATOMIC POWER PLANT AND ITS DEVICE
摘要 PROBLEM TO BE SOLVED: To determine accurately and precisely a core flow from the measured core differential pressure or core support plate differential pressure even when increase of a flow resistance coefficient at a reactor core part is anticipated. SOLUTION: This core flow measuring operation device of an atomic power plant is equipped with a core differential pressure measuring device 44, a core support plate differential pressure measuring device 45, and a differential pressure measuring device 46 between the front and back of a recirculation pump. The core differential pressure, the core support plate differential pressure, and the differential pressure between the front and back of the recirculation pump are measured by each differential pressure measuring device 44, 45, 46 with the passage of time during the reactor operation time. The measured data of the core differential pressure, the core support plate differential pressure, and the differential pressure between the front and back of the recirculation pump are inputted into a process computer 60, and operation processing is performed from the core differential pressure or the core support plate differential pressure by using a core thermal hydraulic power calculation code included beforehand, to thereby determine the core flow or the flow resistance coefficient at the reactor core part. The core flow is corrected in consideration of the increase of the flow resistance coefficient at the reactor core part, and determined accurately and precisely.
申请公布号 JP2003057384(A) 申请公布日期 2003.02.26
申请号 JP20010243003 申请日期 2001.08.09
申请人 TOSHIBA CORP 发明人 FUJII TOSHIHIRO
分类号 G01F1/34;G21C17/032;(IPC1-7):G21C17/032 主分类号 G01F1/34
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