Document Type : Research Paper
Authors
1 Department of Energy Engineering, Sharif University of Technology, P.O.BOX: 14565-1114, Tehran, Iran
2 Department of Energy Engineering, Sharif University of Technology,
3 Chair, Dept. of Energy Engineering, SHARIF Univ. of Technology
Abstract
Abstract: For the neutronic and thermal-hydraulic analysis of nuclear reactors core, it is necessary to develop nuclear computing softwares in order to calculate the neutronic and thermal-hydraulic parameters for the safe operation of them. In this paper, S4HC software was developed for steady-state thermal-hydraulic core calculations using single heated channel method. In order to analyze the core of Bushehr reactor, after calculating neutron parameters by nodal expansion method, thermal-hydraulic analysis of fuel assemblies was performed using S4HC software. After thermal-hydraulic calculations for the fuel assemblies, including the hot fuel assembly, it was concluded that all the thermal-hydraulic parameters of the coolant are within their allowed ranges and the reactor has a good saturation margin.
Abstract: For the neutronic and thermal-hydraulic analysis of nuclear reactors core, it is necessary to develop nuclear computing softwares in order to calculate the neutronic and thermal-hydraulic parameters for the safe operation of them. In this paper, S4HC software was developed for steady-state thermal-hydraulic core calculations using single heated channel method. In order to analyze the core of Bushehr reactor, after calculating neutron parameters by nodal expansion method, thermal-hydraulic analysis of fuel assemblies was performed using S4HC software. After thermal-hydraulic calculations for the fuel assemblies, including the hot fuel assembly, it was concluded that all the thermal-hydraulic parameters of the coolant are within their allowed ranges and the reactor has a good saturation margin.
Keywords
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