Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor

Joo, Seung–Ki; Lee, Jong Bok; Seo, Sang Mun

doi:10.1016/j.net.2017.10.011

Cited by 10 publications

(4 citation statements)

References 2 publications

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“…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.…”

Section: Previous Researchmentioning

confidence: 99%

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

Konishi,

Sasano,

Hayashi

et al. 2024

Applied Sciences

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Nuclear power plants (NPPs) are globally important sources of clean energy. However, high operation and maintenance (O&M) costs are one of the factors hindering the development of NPPs. In this study, we focused on the development of a digital algorithm for ex-core instrumentation systems (EISs) to reduce O&M costs, given that the digitalization of EISs is not progressing compared with other instrumentation and control systems in NPPs. Specifically, we developed a digital algorithm for pulse signal processing in EISs, which traditionally require a significant amount of hardware and maintenance efforts. Our purposes were to simplify the configuration and reduce the O&M costs associated with pulse signal processing. To validate the algorithm, we used a detector emulator and a research reactor. Additionally, we explored a new approach to reduce the workload associated with a discrimination characteristics test (DCT) in EISs. The results of this study demonstrated that the proposed algorithm is effective in achieving good linearity within ±5% of the span and response performance with a delay time of 5 ms, which are required for EISs. Furthermore, the proposed method for the DCT shows promising results in reducing the time required for the test compared with conventional methods.

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Section: Previous Researchmentioning

confidence: 99%

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

Konishi,

Sasano,

Hayashi

et al. 2024

Applied Sciences

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show abstract

“…Preamplification of the detector signals, pulse shaping, the signal-to-noise discrimination, and the mean squared voltage (MSV) calculation are performed by the analog circuits. On the other hand, pulse counting and dead time correction, wide-range logarithmic signal generation with pulse and MSV signals, and the conversion of the neutron flux information to reactor power information are done by digital signal processor unit [9].…”

Section: State-of-the-art Technology For Digital Signal Acquisition Processing Modules and The Digital Enfmsmentioning

confidence: 99%

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

et al. 2020

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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.

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“…Nuclear energy, as a clean, low-carbon and reliable energy source, can alleviate energy shortages and contribute to the reduction of greenhouse gas emissions, playing an indispensable role in the global energy development and transformation process [1][2][3]. After the Fukushima incident in Japan, global nuclear safety agencies imposed higher safety requirements on nuclear power plants [4][5][6][7][8]. The neutron flux rate monitoring system is one of the important components of the reactor safety system.…”

Section: Introductionmentioning

confidence: 99%

“…The neutron flux rate monitoring system is one of the important components of the reactor safety system. The dynamic variation range of nuclear power of the reactor reaches 10 orders of magnitude, and the corresponding variation range of neutron flux rate reaches 11 orders of magnitude from startup to full power operation [7]. For subcritical, control, and safety purposes, it is necessary to monitor the neutron flux rate and its variations in the core of the reactor during all stages of operation.…”

Section: Introductionmentioning

confidence: 99%

Design and characterization of a new high-count wide-range fission chamber based on GEM

Ye,

Zhao,

Wang

et al. 2024

J. Inst.

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As one of the main detectors for monitoring neutron flux rate in a nuclear reactor, the fission chamber (FC) suffers from issues such as low sensitivity, limited counting rate dynamic range, and system mode switching is cumbersome. This study utilizes the advantages of gas electron multipliers (GEM), which are easy to fabricate in large areas and have high counting rates, to design a novel fission chamber. By conducting Monte Carlo simulations on parameters such as the thickness of the 235U coating, the drift distance, and the operating electric field strength, a wide-range fission chamber design that combines high sensitivity and a counting rate range based on GEM has been obtained. The simulation results demonstrated that using a GEM detector to build a fission chamber can significantly improve sensitivity and extend the counting rate range. Subsequently we built a proof-of-concept GEM-based fission chamber and tested it with a 55Fe low-energy X-ray source and an Am-Be neutron source. The results showed that the proof-of-concept detector had a good signal-to-noise ratio and energy linearity, as well as clear discrimination between alpha background and neutron pulse amplitudes.

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Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor

Cited by 10 publications

References 2 publications

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

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

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

Design and characterization of a new high-count wide-range fission chamber based on GEM

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