Employing adaptive fuzzy computing for RCP intelligent control and fault diagnosis

Ashraf Aboshosha; Hisham A. Hamad

doi:10.1007/s41365-023-01288-y

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Employing adaptive fuzzy computing for RCP intelligent control and fault diagnosis

NUCLEAR ELECTRONICS AND INSTRUMENTATION | Updated：2023-10-13

- Employing adaptive fuzzy computing for RCP intelligent control and fault diagnosis
- Nuclear Science and Techniques Vol. 34, Issue 9, Article number: 138(2023)
- Affiliations：
  
  1.Rad. Eng. Dept., Department, NCRRT, Egyptian Atomic Energy Authority, Cairo, Egypt
  2.Electronics Technology Department, Faculty of Technology and Education, Helwan University, Cairo, Egypt
- Author bio：
  
  † ashraf.aboshosha@eaea.org.eg
- Funds：
- DOI：10.1007/s41365-023-01288-y
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Ashraf Aboshosha, Hisham A. Hamad. Employing adaptive fuzzy computing for RCP intelligent control and fault diagnosis. [J]. Nuclear Science and Techniques 34(9):138(2023)
DOI：

Ashraf Aboshosha, Hisham A. Hamad. Employing adaptive fuzzy computing for RCP intelligent control and fault diagnosis. [J]. Nuclear Science and Techniques 34(9):138(2023) DOI： 10.1007/s41365-023-01288-y.

摘要

Abstract

Loss of Coolant Accident (LOCA), Loss of Fluid Accident (LOFA), and Loss of Vacuum Accident (LOVA) are the most severe accidents that can occur in Nuclear Power Reactors (NPRs). These accidents occur when the reactor loses its cooling media, leading to uncontrolled chain reactions akin to a nuclear bomb. This article is focused on exploring methods to prevent such accidents and ensure that the reactor cooling system remains fully controlled. The Reactor Coolant Pump (RCP) has a pivotal role in facilitating heat exchange between the primary cycle, which is connected to the reactor core, and the secondary cycle associated with the steam generator. Furthermore, the RCP is integral to preventing catastrophic events such as LOCA, LOFA, and LOVA accidents. In this study, we discuss the most critical aspects related to the RCP, specifically focusing on RCP control and RCP fault diagnosis. The AI-based adaptive fuzzy method is used to regulate the RCP’s speed and torque, whereas the Neural Fault Diagnosis System (NFDS) is implemented for alarm signaling and fault diagnosis in nuclear reactors. To address the limitations of linguistic and statistical intelligence approaches, an integration of the statistical approach with fuzzy logic has been proposed. This integrated system leverages the strengths of both methods. Adaptive fuzzy control was applied to the VVER 1200 NPR-RCP induction motor, and the NFDS was implemented on the Kori-2 NPR-RCP.

关键词

Keywords

Nuclear Power Plant (NPP)Reactor Coolant PumpFault diagnosisReactor passive safetyNeural networkAdaptive fuzzy

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