Loss of coolant accident analysis under restriction of reverse flow

This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent coolant loss from the bundle inlet due to the reve...

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Main Authors: Majdi I. Radaideh, Tomasz Kozlowski, Yousef M. Farawila
Format: Article
Language:English
Published: Elsevier 2019-09-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573318308465
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spelling doaj-7a9573c07ce242859c6df4ad25e437772020-11-25T02:23:39ZengElsevierNuclear Engineering and Technology1738-57332019-09-0151615321539Loss of coolant accident analysis under restriction of reverse flowMajdi I. Radaideh0Tomasz Kozlowski1Yousef M. Farawila2Department of Nuclear, Plasma and Radiological Engineering, University of Illinois at Urbana-Champaign, Talbot Laboratory, 104 South Wright Street, Urbana, IL, 61801, USA; Corresponding author.Department of Nuclear, Plasma and Radiological Engineering, University of Illinois at Urbana-Champaign, Talbot Laboratory, 104 South Wright Street, Urbana, IL, 61801, USAFarawila et al., Inc., 306 Rockwood, Richland, WA, 99352, USAThis paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent coolant loss from the bundle inlet due to the reverse flow after a large break in the recirculation loop. The device allows for flow in the forward direction which occurs during normal operation, while after the break, the RFRD device changes its status to prevent reverse flow. In this paper, a detailed simulation of LOCA has been carried out using the U.S. NRC's TRACE code to investigate the effect of RFRD on the flow rate as well as peak clad temperature of BWR fuel bundles during three different LOCA scenarios: small break LOCA (25% LOCA), large break LOCA (100% LOCA), and double-ended guillotine break (200% LOCA). The results demonstrated that the device could substantially block flow reversal in fuel bundles during LOCA, allowing for coolant to remain in the core during the coolant blowdown phase. The device can retain additional cooling water after activating the emergency systems, which maintains the peak clad temperature at lower levels. Moreover, the RFRD achieved the reflood phase (when the saturation temperature of the clad is restored) earlier than without the RFRD. Keywords: LOCA, Reverse flow, TRACE, BWR, Thermal-hydraulichttp://www.sciencedirect.com/science/article/pii/S1738573318308465
collection DOAJ
language English
format Article
sources DOAJ
author Majdi I. Radaideh
Tomasz Kozlowski
Yousef M. Farawila
spellingShingle Majdi I. Radaideh
Tomasz Kozlowski
Yousef M. Farawila
Loss of coolant accident analysis under restriction of reverse flow
Nuclear Engineering and Technology
author_facet Majdi I. Radaideh
Tomasz Kozlowski
Yousef M. Farawila
author_sort Majdi I. Radaideh
title Loss of coolant accident analysis under restriction of reverse flow
title_short Loss of coolant accident analysis under restriction of reverse flow
title_full Loss of coolant accident analysis under restriction of reverse flow
title_fullStr Loss of coolant accident analysis under restriction of reverse flow
title_full_unstemmed Loss of coolant accident analysis under restriction of reverse flow
title_sort loss of coolant accident analysis under restriction of reverse flow
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2019-09-01
description This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent coolant loss from the bundle inlet due to the reverse flow after a large break in the recirculation loop. The device allows for flow in the forward direction which occurs during normal operation, while after the break, the RFRD device changes its status to prevent reverse flow. In this paper, a detailed simulation of LOCA has been carried out using the U.S. NRC's TRACE code to investigate the effect of RFRD on the flow rate as well as peak clad temperature of BWR fuel bundles during three different LOCA scenarios: small break LOCA (25% LOCA), large break LOCA (100% LOCA), and double-ended guillotine break (200% LOCA). The results demonstrated that the device could substantially block flow reversal in fuel bundles during LOCA, allowing for coolant to remain in the core during the coolant blowdown phase. The device can retain additional cooling water after activating the emergency systems, which maintains the peak clad temperature at lower levels. Moreover, the RFRD achieved the reflood phase (when the saturation temperature of the clad is restored) earlier than without the RFRD. Keywords: LOCA, Reverse flow, TRACE, BWR, Thermal-hydraulic
url http://www.sciencedirect.com/science/article/pii/S1738573318308465
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