Scram characteristics of the control rods of a pressurized water reactor under seismic conditions.
Katsuhisa Fujita, Yoshikazu Shinohara, Kiyoshi Nanbu, T. Nakatogawa, Tomonori NOMURA
Abstract
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Katsuhisa Fujita, Yoshikazu Shinohara, Kiyoshi Nanbu, T. Nakatogawa, Tomonori NOMURA
Abstract
Open-access reader
Control rod drop verification experiments of a pressurized water reactor under seismic conditions are performed to confirm the insertion function of control rods into a core. To evaluate these tests, computer simulations are performed. A fuel assembly, control rods, guide tube and other associated structures are immersed in a water tank, and shaken by four hydraulic shakers. The scram time of control rods under seismic conditions was measured, and confirmed to meet the scram function. Moreover, vibrational response characteristics of core structure and dropping behavior of control rods in consideration of collisions are calculated by using a finite difference method. The behavior of the dropping control rods and the scram time obtained by the computer simulation show a very good agreement with the verification experimental results.
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Control rod drop verification experiments of a pressurized water reactor under seismic conditions are performed to confirm the insertion function of control rods into a core. To evaluate these tests, computer simulations are performed. A fuel assembly, control rods, guide tube and other associated structures are immersed in a water tank, and shaken by four hydraulic shakers. The scram time of control rods under seismic conditions was measured, and confirmed to meet the scram function. Moreover, vibrational response characteristics of core structure and dropping behavior of control rods in consideration of collisions are calculated by using a finite difference method. The behavior of the dropping control rods and the scram time obtained by the computer simulation show a very good agreement with the verification experimental results.
Key concepts: Scram, Control rod, Rod, Core (optical fiber), Pressurized water reactor, Nuclear engineering, Materials science, Structural engineering