1) Center for Nuclear Technology Assessment - BATAN
2) Department of Nuclear Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya464-01 JAPAN
3) Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki 319-11 JAPAN
ABSTRACT
THERMAL HYDRAULIC EXPERIMENT TO TEST THE STABLE OPERATION OF A PIUS TYPE REACTOR. An advanced type of reactor concept as the Process Inherent Ultimate Safety (PIUS) reactor was based on intrinsically passive safety considerations. The stable operation of a PIUS type reactor is based on the automation of circulation pump speed. An automatic circulation pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS type reactor. In principle this control system maintains the fluid temperature at the axial center of the lower density lock at average of the fluid temperatures below and above the lower density lock. This control system will prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments using atmospheric pressure thermal hydraulic test loop which simulated the PIUS principle. The experiments such as: start up and power ramping tests for normal operation simulation and a loss of feedwater test for an accident condition simulation, carried out in JAERI.
Keywords : Thermal-Hydraulic Experiment, PIUS type Reactor, Passive Safety, Pump Speed Control System, Density Lock, Start-Up Simulation Test, Power Ramping Test, Loss of Feedwater Test
Published : Proceeding "Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan Dan Teknologi Nuklir", Yogyakarta, 25-27 Oktober 1995, ISSN 0216-3128
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