THERMAL-HYDRAULIC EXPERIMENT FOR SAFE AND STABLE OPERATION OF A PIUS-TYPE REACTOR

THERMAL-HYDRAULIC EXPERIMENT FOR SAFE AND STABLE OPERATION OF A PIUS-TYPE REACTOR
K.Tasaka¹⁾, S.Imai¹⁾, H.Masaoka¹⁾, Ign. Djoko Irianto¹⁾, H.Kohketsu¹⁾, M.Tamaki¹⁾, Y.Anoda²⁾, H.Murata²⁾ and Y.Kukita^2)
1) Department of Nuclear Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya464-01 JAPAN
²⁾ Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki 319-11 JAPAN
ABSTRACT
A new automatic pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the density lock in order to 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 experiment such as start-up and power ramping tests for normal operation simulation and a loss of feedwater test for an accident condition simulation, using a small scale atmospheric pressure test loop which simulated the PIUS principle.

Keywords : Pump speed control system, density lock, PIUS-type reactor, start-up test, power ramping test, normal operation simulation, accident condition simulation
Published : Proceedings of "International Conference on Design and Safety of Advanced Nuclear Power Plant", Tokyo, Japan, October 25-29, 1992