Abstract
Abstract A measuring method of core flow rate in the Advanced Boiling Water Reactor (ABWR), which equips Reactor Internal Pumps (RIPs) for reactor coolant recirculation, were evaluated by 1/5 scaled model tests and turbulent analyses. The conclusions obtained are as follows: (1) An interrelationship among RIPs was so weak that ABWR core flow was derived accurately as the summation of the individual RIP flow rate, which was estimated from each pump O-H characteristics (Q: pump flow rate, H: differential pressure head along the RIP's upstream and downstream). Measurement accuracy of core flow was confirmed to meet the requirements for expected ABWR operating conditions. Furthermore, it appeared likely that the requirements should be satisfied even in hypothetical operating states, namely operation with one pump out of service. (2) It was also confirmed that the turbulent flow analysis was useful to estimate the flow pattern near the RIPs.
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