Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor
Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemen...
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Elsevier
2016-10-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S173857331630047X |
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doaj-bec6be16cef84e4caf18f5c1d9e714fa2020-11-24T23:14:23ZengElsevierNuclear Engineering and Technology1738-57332016-10-014851174118310.1016/j.net.2016.04.002Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water ReactorMehdi Dehjourian0Reza Sayareh1Mohammad Rahgoshay2Gholamreza Jahanfarnia3Amir Saied Shirani4Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran, Tehran, IranFaculty of Electrical and Computer Engineering, Kerman Graduate University of Technology, Kerman, IranDepartment of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran, Tehran, IranDepartment of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran, Tehran, IranFaculty of Engineering, Shahid Beheshti University, Tehran, IranHydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.http://www.sciencedirect.com/science/article/pii/S173857331630047XCore Concrete InteractionLoss of Coolant AccidentMELCORPassive Autocatalytic RecombinerPressurized Water ReactorSevere Accident |
| collection |
DOAJ |
| language |
English |
| format |
Article |
| sources |
DOAJ |
| author |
Mehdi Dehjourian Reza Sayareh Mohammad Rahgoshay Gholamreza Jahanfarnia Amir Saied Shirani |
| spellingShingle |
Mehdi Dehjourian Reza Sayareh Mohammad Rahgoshay Gholamreza Jahanfarnia Amir Saied Shirani Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor Nuclear Engineering and Technology Core Concrete Interaction Loss of Coolant Accident MELCOR Passive Autocatalytic Recombiner Pressurized Water Reactor Severe Accident |
| author_facet |
Mehdi Dehjourian Reza Sayareh Mohammad Rahgoshay Gholamreza Jahanfarnia Amir Saied Shirani |
| author_sort |
Mehdi Dehjourian |
| title |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor |
| title_short |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor |
| title_full |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor |
| title_fullStr |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor |
| title_full_unstemmed |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor |
| title_sort |
investigation of a hydrogen mitigation system during large break loss-of-coolant accident for a two-loop pressurized water reactor |
| publisher |
Elsevier |
| series |
Nuclear Engineering and Technology |
| issn |
1738-5733 |
| publishDate |
2016-10-01 |
| description |
Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated. |
| topic |
Core Concrete Interaction Loss of Coolant Accident MELCOR Passive Autocatalytic Recombiner Pressurized Water Reactor Severe Accident |
| url |
http://www.sciencedirect.com/science/article/pii/S173857331630047X |
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