Analysis of Rotor-Seizure-Induced Pressure Rise in a Nuclear Reactor Primary Cooling Loop

Haoyu Cui¹, Congxin Yang^1,2,*, Yanlei Guo¹, Tianzhi Lv¹, Sen Zhao¹
1 College of Energy and Power Engineering, Lanzhou University of Technology, Lanzhou, 730050, China
2 Key Laboratory of Fluid Machinery and System of Gansu Province, Lanzhou, 730050, China
* Corresponding Author: Congxin Yang. Email: email
(This article belongs to the Special Issue: Computational Fluid Dynamics: Two- and Three-dimensional fluid flow analysis over a body using commercial software)

Fluid Dynamics & Materials Processing https://doi.org/10.32604/fdmp.2024.055301

Received 22 June 2024; Accepted 09 September 2024; Published online 05 October 2024

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Abstract

Most of existing methods for the safety assessment of the primary cooling loop of nuclear reactors in conditions of reactor coolant pump (RCP) failure (rotor seizure accident) essentially rely on the combination of one-dimensional theory and experience. This study introduces a novel three-dimensional model of the ‘Hualong-1’ (HPR1000) primary loop and uses the method of matching the resistance characteristics of the tube to ensure that the main pump operates at the rated operating condition. In particular, the three-dimensional unsteady numerical calculation of the RCP behavior in the rotor-seizure accident condition is carried out in the framework of the RNG k-ε turbulence model. The related transient pressure surge law and hydraulic load response are obtained accordingly.

Keywords

Axial-flow reactor coolant pump; reactor primary loop; rotor seizure accident condition; pressure surge; hydraulic load

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Analysis of Rotor-Seizure-Induced Pressure Rise in a Nuclear Reactor Primary Cooling Loop

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