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Additional resources for Appl of PCs to Enhance Oper, Mgmt of Research Reactors (IAEA TECDOC-1004)
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.
By neglecting the pool water velocity, the pressure drop is expressed as follows: APd = 8u 12 The total pressure drop through a fuel element consists of losses in upper and lower boxes of the fuel element and the friction pressure drop on the surface of fuel plates. These losses are in addition to the losses due to the change in height between core inlet and outlet. Mam part of the pressure drop results from the fricition loss in the cooling channels. Two different approaches for the calculation of friction losses are being outlined.
According to this expression an increase of heat production or decrease of inlet subcooling (Tsat - T^ ) aggravates flow instability and lessen the safety margin. Using the expression for Sf the HEATHYD code calculates the safety margin to the onset of flow instability which is printed out for each cooling channel. e. R (T^ - Tm) , specific heat, and flow rate. 05 [ R8 Cp tw (W tw / WHLH ) U (Tsat - Tin) ] In this correlation the effect of channel entrance loss, which is a stabilizing factor for the system, is not included.