Modeling of Forced and Natural Circulation Test Loop for a Pressurized Water Reactor using Thermal-Hydraulic Method

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Khonsha Iman

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Journal Paper

Paper Information

Journal: CHEMICAL PROCESS DESIGN Year:2026 | Volume:5 | Issue:1 Page(s): 96-110

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Information Journal Paper

Title

Modeling of Forced and Natural Circulation Test Loop for a Pressurized Water Reactor using Thermal-Hydraulic Method

Author(s)

Khonsha Iman | Issue Writer Certificate

Keywords

Modeling

Forced and Natural Circulation

Test Loop

Pressurized Water Reactor

RELAP5/MOD3.2

Abstract

The present paper studies an Integral Test Facility (ITF) using the thermal-hydraulic method in order to determine its safety and reliability. The scaling and thermal-hydraulic design of the Islamic Azad University Test Loop (IAUTL) is conducted, accompanied by the energy scaling methodology for a typical pressurized water reactor (PWR). The scaling findings are authenticated by the experimental data resulting from the pressurized water reactor for pure water and forced circulation (FC) flow in 100% of core nominal power using the RELAP5/MOD3.2 code. From the comparison of the simulation results of core temperature in natural and forced flow, it can be concluded that the maximum outlet temperature of the reactor core in natural and forced flow is 169.4 °C and 174 °C, respectively. This temperature increase in natural flow is due to the increase in the residence time of the fluid in the natural flow regime around the core. Also, the temperature drop in the heat exchanger in natural and forced flow is 20 °C and 13 °C, respectively. This increase in heat loss in natural flow is due to the lower velocity of the natural flow and, as a result, the heat exchange also increases in natural flow. The pressure drop between the inlet and outlet of the reactor core, in both free and forced flow, is approximately 2 bar. The simulation results indicate that the IAUTL core can remove the residual heat from the core using NC flow.

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