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Additional resources for Appl of PCs to Enhance Oper, Mgmt of Research Reactors (IAEA TECDOC-1004)
Stores inventory programme, Fuel 57 assembly history programme and Reactor daily performance report. All these packages have been developed in FOXPRO environment with user-friendly pop-up menus and help levels at every stage. These programmes are accessible from all the nodes connected on the LAN. Provisions also exist to incorporate extra features in this system in future by augmenting the capacity of the Front-end system. The proposed applications include logging of important system parameters such as individual fuel channel coolant outlet temperature, channel coolant flow and channel power output etc..
The primary coolant circuit consists of three identical heavy water recirculating loops. Heavy water inside the reactor vessel serves as moderator & reflector and the heavy water in the coolant, moderator and the reflector regions is intermixed. Reactor power is controlled by controlling moderator level in the reactor vessel. Demineralised water is used as secondary coolant in a closed loop. The secondary coolant is cooled by sea water in a separate set of heat exchangers. A simplified flow sheet of the coolant system is shown in Fig -1.
_ _ 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.