An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel

Nuclear power plants contain several monitoring systems that can identify the in-vessel phenomena of a severe accident (SA). Though a lot of analysis and research is carried out on SA, right from the development of the nuclear industry, not all the possible circumstances are taken into consideration...

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Main Authors: Anil Kumar Khambampati, Kyung Youn Kim, Seop Hur, Sung Joong Kim, Jung Taek Kim
Format: Article
Language:English
Published: Elsevier 2021-02-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320308093
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spelling doaj-ef2141b399ce456c9cb7eeb901bdbe552021-01-22T04:49:29ZengElsevierNuclear Engineering and Technology1738-57332021-02-01532532548An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vesselAnil Kumar Khambampati0Kyung Youn Kim1Seop Hur2Sung Joong Kim3Jung Taek Kim4Department of Electronic Engineering, Jeju National University, South KoreaDepartment of Electronic Engineering, Jeju National University, South Korea; Corresponding author.Research Div. of Autonomous Control, Korea Atomic Energy Research Institute, South KoreaDepartment of Nuclear Engineering, Hanyang University, South KoreaResearch Div. of Autonomous Control, Korea Atomic Energy Research Institute, South Korea; Corresponding author.Nuclear power plants contain several monitoring systems that can identify the in-vessel phenomena of a severe accident (SA). Though a lot of analysis and research is carried out on SA, right from the development of the nuclear industry, not all the possible circumstances are taken into consideration. Therefore, to improve the efficacy of the safety of nuclear power plants, additional analytical studies are needed that can directly monitor severe accident phenomena. This paper presents an interacting multiple model (IMM) based fault detection and diagnosis (FDD) approach for the identification of in-vessel phenomena to provide the accident propagation information using reactor vessel (RV) out-wall temperature distribution during severe accidents in a nuclear power plant. The estimation of wall temperature is treated as a state estimation problem where the time-varying wall temperature is estimated using IMM employing three multiple models for temperature evolution. From the estimated RV out-wall temperature and rate of temperature, the in-vessel phenomena are identified such as core meltdown, corium relocation, reactor vessel damage, reflooding, etc. We tested the proposed method with five different types of SA scenarios and the results show that the proposed method has estimated the outer wall temperature with good accuracy.http://www.sciencedirect.com/science/article/pii/S1738573320308093Interactive multiple modelFault detectionState estimationIdentification of in-vessel phenomenaRV out-wall temperature
collection DOAJ
language English
format Article
sources DOAJ
author Anil Kumar Khambampati
Kyung Youn Kim
Seop Hur
Sung Joong Kim
Jung Taek Kim
spellingShingle Anil Kumar Khambampati
Kyung Youn Kim
Seop Hur
Sung Joong Kim
Jung Taek Kim
An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
Nuclear Engineering and Technology
Interactive multiple model
Fault detection
State estimation
Identification of in-vessel phenomena
RV out-wall temperature
author_facet Anil Kumar Khambampati
Kyung Youn Kim
Seop Hur
Sung Joong Kim
Jung Taek Kim
author_sort Anil Kumar Khambampati
title An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
title_short An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
title_full An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
title_fullStr An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
title_full_unstemmed An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
title_sort interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-02-01
description Nuclear power plants contain several monitoring systems that can identify the in-vessel phenomena of a severe accident (SA). Though a lot of analysis and research is carried out on SA, right from the development of the nuclear industry, not all the possible circumstances are taken into consideration. Therefore, to improve the efficacy of the safety of nuclear power plants, additional analytical studies are needed that can directly monitor severe accident phenomena. This paper presents an interacting multiple model (IMM) based fault detection and diagnosis (FDD) approach for the identification of in-vessel phenomena to provide the accident propagation information using reactor vessel (RV) out-wall temperature distribution during severe accidents in a nuclear power plant. The estimation of wall temperature is treated as a state estimation problem where the time-varying wall temperature is estimated using IMM employing three multiple models for temperature evolution. From the estimated RV out-wall temperature and rate of temperature, the in-vessel phenomena are identified such as core meltdown, corium relocation, reactor vessel damage, reflooding, etc. We tested the proposed method with five different types of SA scenarios and the results show that the proposed method has estimated the outer wall temperature with good accuracy.
topic Interactive multiple model
Fault detection
State estimation
Identification of in-vessel phenomena
RV out-wall temperature
url http://www.sciencedirect.com/science/article/pii/S1738573320308093
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