Reactivity feedback effect on loss of flow accident in PWR

In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents. A thermal-hydraulic code coupled with a point reactor kinetic model are used for these calculations; where kinetics...

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Main Authors: Basma Foad, Salwa H. Abdel-Latif, Toshikazu Takeda
Format: Article
Language:English
Published: Elsevier 2018-12-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573317304448
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spelling doaj-0598d6c268e542d2b8877e86d4909a262020-11-25T00:57:51ZengElsevierNuclear Engineering and Technology1738-57332018-12-0150812771288Reactivity feedback effect on loss of flow accident in PWRBasma Foad0Salwa H. Abdel-Latif1Toshikazu Takeda2Egypt Nuclear and Radiological Regulatory Authority, 3 Ahmad El Zomar St., Nasr City, Cairo, 11787, Egypt; Research Institute of Nuclear Engineering, University of Fukui, Kanawa-cho 1-2-4, Tsuruga-shi, Fukui-ken, 914-0055, Japan; Corresponding author. Egypt Nuclear and Radiological Regulatory Authority, 3 Ahmad El Zomar St., Nasr City, Cairo, 11787, Egypt.Egypt Nuclear and Radiological Regulatory Authority, 3 Ahmad El Zomar St., Nasr City, Cairo, 11787, EgyptResearch Institute of Nuclear Engineering, University of Fukui, Kanawa-cho 1-2-4, Tsuruga-shi, Fukui-ken, 914-0055, JapanIn this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents. A thermal-hydraulic code coupled with a point reactor kinetic model are used for these calculations; where kinetics parameters have been developed from the neutronic SRAC code to provide inputs to RELAP5-3D code to calculate parameters related to safety and guarantee that they meet the regulatory requirements. In RELAP5-3D the reactivity feedback is computed by both separable and tabular models. The results show the importance of the reactivity feedback on calculating the power which is the key parameter that controls the clad and fuel temperatures to maintain them below their melting point and therefore prevent core melt. In addition, extending modeling capability from separable to tabular model has nonremarkable influence on calculated safety parameters. Keywords: CLOFA, RELAP5-3D code, Reactor kinetics, PWRhttp://www.sciencedirect.com/science/article/pii/S1738573317304448
collection DOAJ
language English
format Article
sources DOAJ
author Basma Foad
Salwa H. Abdel-Latif
Toshikazu Takeda
spellingShingle Basma Foad
Salwa H. Abdel-Latif
Toshikazu Takeda
Reactivity feedback effect on loss of flow accident in PWR
Nuclear Engineering and Technology
author_facet Basma Foad
Salwa H. Abdel-Latif
Toshikazu Takeda
author_sort Basma Foad
title Reactivity feedback effect on loss of flow accident in PWR
title_short Reactivity feedback effect on loss of flow accident in PWR
title_full Reactivity feedback effect on loss of flow accident in PWR
title_fullStr Reactivity feedback effect on loss of flow accident in PWR
title_full_unstemmed Reactivity feedback effect on loss of flow accident in PWR
title_sort reactivity feedback effect on loss of flow accident in pwr
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2018-12-01
description In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents. A thermal-hydraulic code coupled with a point reactor kinetic model are used for these calculations; where kinetics parameters have been developed from the neutronic SRAC code to provide inputs to RELAP5-3D code to calculate parameters related to safety and guarantee that they meet the regulatory requirements. In RELAP5-3D the reactivity feedback is computed by both separable and tabular models. The results show the importance of the reactivity feedback on calculating the power which is the key parameter that controls the clad and fuel temperatures to maintain them below their melting point and therefore prevent core melt. In addition, extending modeling capability from separable to tabular model has nonremarkable influence on calculated safety parameters. Keywords: CLOFA, RELAP5-3D code, Reactor kinetics, PWR
url http://www.sciencedirect.com/science/article/pii/S1738573317304448
work_keys_str_mv AT basmafoad reactivityfeedbackeffectonlossofflowaccidentinpwr
AT salwahabdellatif reactivityfeedbackeffectonlossofflowaccidentinpwr
AT toshikazutakeda reactivityfeedbackeffectonlossofflowaccidentinpwr
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