Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

Abstract

This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV.

Digitalization of Pulse Signal Processing for Ex-Core Instrumentation System in Nuclear Power Plants

“…There have been studies regarding the digitalization of EISs [10][11][12]. Kim et al [10] proposed methods for processing pulse signals and the mean square value output of a fission chamber (FC) in the digital-signal-processing unit. Mjzoob et al [11] aimed to digitalize the Intermediate Range (IR).…”