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K. N. D. K. AGARWAL Reactor Group, Bhabha Atomic Research Centre, Trombay, Mumbai, India Abstract The on-line use of Personal Computers in research reactors, with custom made applications for aiding the operators in analyzing plant conditions under normal and abnormal situations, has become extremely popular. A system has been developed to monitor and evaluate important parameters for the research reactor DHRUVA, a 100 MW research reactor located at the Bhabha Atomic Research Centre, Trombay. The system was essentially designed for on-line computation of the following parameters: reactor thermal power, reactivity load due to Xenon, core reactivity balance and performance monitoring of shut-down devices.

S. Sharma : Reactor chemistry section. JUN Korea Atomic Energy Research Institute, Reactor Operations Division, Seoul, Republic of Korea Abstract Development of research reactor parameter measuring system based on a personal computer was carried out at the Korea Atomic Research Institute. The work includes the interface construction between a PC and reactor instruments, experimental logic development, programming and test. At first, various reactor experiments were reviewed to identify signal type, dynamic range and number of channels.

_.. _ . _ _ 30 40 _ . „ _ _ _L. 50 ACTIVE LENGTH (MM) Fig, 8: Axial variation of heat flux at ONB and DNB in comparison to actual heat flux for hot channel case 60 The results of calculations show that the safety margin to flow intability represents the limiting parameter regarding safe design and operation. 47. C° Entrance Pressure Loss Coefficient (Dimensionless) Exit Pressure Loss Coefficient (Dimensionless) Length of Fuel plate (Coolant Channel) cm Nf Number of Fueled Plates (Dimensionless) PZ Pressure of Coolant at any Point nz" bar abs P Pressure at Channel Exit bar abs Critical Pressure of Coolant bar abs Pressure Loss at Channel Entrance bar Pressure Loss at Channel Exit bar Pressure Loss Through Channel due to Fricition bar Dynamic Pressure Loss bar Symbol AC a r /-* Hco k Ken Kex LC PC APen APex APf APd 46 2 2 NOMENCLATURE (cont) Total Pressure Loss bar Prandtls Number (Dimensionless) q Local Heat Flux w/cm qa qoNB qoFi Axial Average Heat Flux w/cm Heat Flux at Onset of Nucleate Boiling w/cm Heat Flux at Onset of Flow Instability w/cm qc Burnout (Critical) Heat Flux Q Volumetric Flow Through the Element w/cm 3 m /hr Reynolds Number (Dimensionless) Water Temperature at Core Inlet C° Water Temperature at Core Outlet C° Water Temperature Rise in the Coolant Channel C° Saturation Temperature of Water C° Clad Surfache Temperature C° Tfl Fluid Temperature C° ATsub Water Subcooling C° Fuel Meat Thickness cm Fuel Plate Thickness cm Water Channel Thickness cm U Water Velocity in the Channel m/sec U0 Water Velocitiy just beyond the Channel m/sec Critical Velocity m/sec W Water Channel Width cm wh Effective Fuel Plate Width for Heat Transfer cm Wp Total Plate Width of Chord of Curved Plate cm z Axial Location along the Channel cm X Heat Vaporization KJ/Kg u Dynamic Viscosity of Water Pa.

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