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Aizawa, Kosuke; Ueki, Yoshitaka*
Proceedings of Specialist Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal-Hydraulics and Severe Accidents (SWINTH-2024) (USB Flash Drive), 7 Pages, 2024/06
Early detection of an anomaly greatly enhances the safety of nuclear power plants. A detection system called an acoustic measurement has high responsiveness, because sound produced by the anomaly is transmitted from the place at which an anomaly has occurred to a measurement point at a speed of sound, and the acoustic measurement has the potential to directly detect the physical quantity of an anomaly at its occurrence point. For sodium-cooled fast reactors, we have been developing an anomaly detection technique using the acoustic measurement that offers these features. This paper clarifies issues in applying the acoustic measurement to a sodium-cooled fast reactor, how we solve the issues, and the current status of this research.
4 simulated fuel bundle for validation of thermal-hydraulics simulation codesOno, Ayako; Nagatake, Taku; Uesawa, Shinichiro; Shibata, Mitsuhiko; Yoshida, Hiroyuki
Proceedings of Specialist Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal-Hydraulics and Severe Accidents (SWINTH-2024) (USB Flash Drive), 7 Pages, 2024/06
Japan Atomic Energy Agency (JAEA) is developing a neutronics/thermal-hydraulics coupling simulation code for light-water reactors. Thermal-hydraulic simulation codes applied to the coupling code are expected to calculate the void fraction distribution in a rod bundle under operational conditions, which are necessary for neutron transport simulation, and need to be validated using void fraction distribution data in a rod bundle under high-temperature and high-pressure conditions. Therefore, we have conducted the measurement of the instantaneous void distribution in the 4 4 simulated fuel bundle using a developed wire mesh sensor, which is installed in the pressurized two-phase flow experimental loop of JAEA to obtain the data for code validation.
Kitagaki, Toru; Morreale, A.*; Ikeuchi, Hirotomo; Koyama, Shinichi
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