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Additional info for Appl of PCs to Enhance Oper, Mgmt of Research Reactors (IAEA TECDOC-1004)
RESULTS OF FLUID FLOW AND HEAT TRANSFER CALCULATION USING HEATHYDCODE PARAMETERS Coolant velocity (m/sec NOMINAL POWER AVERAGE / HOT OVER POWER AVERAGE / HOT 4,08 4,081 4,080 4,082 (a) dynamic (bar) 0,082 0,083 0,082 0,083 (b) gravitation (bar) 0,059 0,059 0,059 0,059 (c) friction (bar) 0,028 0,273 0,276 0,272 (d) inlet (bar) 0,024 0,024 0,024 0,240 Total pressure drop across core (bar) 0,442 0,438 0,442 0,438 Pressure at channel exit (bar) 1,555 1,559 1,555 1,559 Pressure drop: Saturation temperature at channel exit (°C) 112,46 112,53 112,54 112,54 Coolant temperature rise across the channel (°C) 10,46 33,14 12,09 37,79 Peak clad temperature (°C)* 73,93 134,40 78,30 145,60 Average heat flux (w/cm2) 38,03 118,65 43,36 135,26 Peak heat flux (w/cm2) 62,67 195,56 71,46 222,93 2,59 0,80 2,28 0,69 (a) to Departure from Nucleate Boiling (DNB) 7,47 2,27 6,53 1,96 (b) to Onset of Flow Instability (OFI) 5,24 1,68 4,59 1,47 Margin to Onset of Nucleate Boiling (ONB) Safety margin: * Using Haussen II Correlation In the hot channel case, the graph includes the saturation temperature that has been partly exceeded by the clad surface temperature with the result of subcooled boiling.
The calculation of heat transfer coefficients takes place in the subroutine ALPHA using the following relationship: k h= —— Nu D Nu ist referred to the Nusselt number as a dimensionless parameter characterizing both the physical properties of the coolant and dynamic characteristics of the flow. For the turbulant flow in the cooling channels of the core, different empirical correlations for Nu are available. All correlations are expressed as a function of Reynolds number Re ,specifying hydraulic condition and prandtl number Pr, for physical properties of the coolant.
38 III. Application of the HEATHYD code After completing experimental verification of the HEATHYD model, it was applied to calculate the thermohydraulics of a plate type MTR. It was assumed that the core consists of 48 Fuel elements generating a total power of 30 MW. 4 m3/h (for each fuel element) was assumed. As inlet coolant temperature, 40 °C and a pressure of 2 bar were applied as main initial thermohydraulic data(Table 1). The main results of the HEATHYD calculation have been compiled on Table 2 for the average and hot channel case at nominal power and overpower of the 114 %, respectively.