Determination of Mass Flow Rates from Measured In-Core Two-Phase Flow Transit Times in a Boiling Water Reastor

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概要

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• By analysing the neutron noise signals of the in-core detectors, the two-phase flow transit times have been measured for unit 1 of Tarapur Atomic Power Station (General Electric Boiling Water Reactor). Our study has shown that it is reasonable to identify the fluid velocity derived from the measured transit time with the volumetric flux. This interpretation offers the advantage of determining the mass flow rate by using the measured transit time and the steam quality obtained by the heat balance. Further, it is feasible to infer gross flow rate changes by combining the calculated value of the transit time as a function of flow with the periodic measurements of transit time over the operating cycle of the reactor.

• 社団法人 日本原子力学会の論文
• 1995-05-25

著者

• Kulkarni A.

  Bhabha Atomic Research Centre

• CHAUDHARY V.

  Bhabha Atomic Research Centre

• ARORA K.

  Bhabha Atomic Research Centre

• POTTI Thankam

  Reactor Physics and Nuclear Engineering Section, Reactor group

• Potti Thankam

  Reactor Physics And Nuclear Engineering Section Reactor Group

関連論文

• Determination of Mass Flow Rates from Measured In-Core Two-Phase Flow Transit Times in a Boiling Water Reastor

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