NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090602(2024)

Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors

Siqin HU1,2, Chong ZHOU1,2、*, Guifeng ZHU1,2, Yang ZOU1,2, Xiaohan YU1,2, and Shuaiyu XUE1,2
Author Affiliations
  • 1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
  • 2University of Chinese Academy of Sciences, Beijing 100049, China
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    Background

    Compared with traditional components, novel dual cooled assemblies for liquid-fuel molten salt reactors demonstrate a lower graphite hot spot temperature owing to their increased heat transfer area and reduced graphite thermal conduction distance. However, owing to the distinct geometric characteristics and spontaneous heating of liquid fuel, unique heat division and flow distribution patterns occur between the internal and external channels in dual cooled assemblies.

    Purpose

    This study aims to develop new computational analysis tools to estimate the thermal-hydraulic performance of these assemblies.

    Methods

    This study developed a one-dimensional steady-state thermal-hydraulic analysis code, namely Thermal-Hydraulic Analysis Code for Dual Cooled Assembly-Molten Salt Reactor (THDA-MSR) using the MATLAB platform. Considering the spontaneous heating of the fuel salt, a one-dimensional temperature distribution model for liquid fuel and a he at transfer model between the fuel salt and graphite were established. A flow distribution model was developed based on the principle of equal pressure drops in parallel channels. Additionally, numerical simulations were performed using computational fluid dynamics (CFD) software to validate the code results.

    Results

    The study demonstrates a strong agreement between the THDA-MSR and CFD results, with a pressure drop deviation and maximum graphite temperature deviation below 4.84% and 0.15%, respectively. The analysis shows that the ratio of the external channel is the key parameter affecting the maximum outlet temperature of the fuel salt and the maximum temperature of graphite.

    Conclusions

    The model is applicable for thermal-hydraulic calculations and analysis of dual cooled assemblies in liquid-fuel molten salt reactors.

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    Siqin HU, Chong ZHOU, Guifeng ZHU, Yang ZOU, Xiaohan YU, Shuaiyu XUE. Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090602

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Nov. 16, 2023

    Accepted: --

    Published Online: Nov. 13, 2024

    The Author Email:

    DOI:10.11889/j.0253-3219.2024.hjs.47.090602

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