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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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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1725222586546126848 |