Steady-state analysis of neutronic and thermal-hydraulic for Bushehr nuclear reactor’s fuel assemblies using nodal expansion and single heated channel method

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Naghavi Dizaji D.; Kolali A.; Vosoughi N.

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Journal Paper

Paper Information

Journal: JOURNAL OF NUCLEAR SCIENCE, ENGINEERING AND TECHNOLOGY Year:2024 | Volume:45 | Issue:3 Page(s): 13-21

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Information Journal Paper

Title

Steady-state analysis of neutronic and thermal-hydraulic for Bushehr nuclear reactor’s fuel assemblies using nodal expansion and single heated channel method

Author(s)

Naghavi Dizaji D. | Kolali A. | Vosoughi N. | Issue Writer Certificate

Keywords

Neutronic and Thermal-hydraulic Analysis

Single Heated Channel

High-order Nodal Expansion Method

S4HC

Bushehr Nuclear Reactor

Abstract

For the neutronic and thermal-hydraulic analysis of nuclear reactor cores, it is necessary to develop nuclear computing software to calculate neutronic and thermal-hydrodynamic parameters for their safe operation. In this paper, S4HC software was developed for steady-state thermal-hydraulic core calculations using a single heated channel method. To analyze the Bushehr reactor core, after calculating neutron parameters by the nodal expansion method, a 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 coolant thermal-hydraulic parameters are within their allowed ranges and the reactor has sufficient saturation margins.

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