Thermal hydraulic analysis of core flow bypass in a typical research reactor
The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe condition with enough safety margins during normal operation and anticipated operational occurrences. In this research, core flow bypass is studied under the conditions of the unavailability of safety sy...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2019-02-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573318302559 |
| _version_ | 1819084520269283328 |
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| author | Said M.A. Ibrahim Salah El-Din El-Morshedy Abdelfatah Abdelmaksoud |
| author_facet | Said M.A. Ibrahim Salah El-Din El-Morshedy Abdelfatah Abdelmaksoud |
| author_sort | Said M.A. Ibrahim |
| collection | DOAJ |
| description | The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe condition with enough safety margins during normal operation and anticipated operational occurrences. In this research, core flow bypass is studied under the conditions of the unavailability of safety systems. As core bypass occurs, the core flow rate is assumed to decrease exponentially with a time constant of 25 s to new steady state values of 20, 40, 60, and 80% of the nominal core flow rate. The thermal hydraulic code PARET is used through these calculations. Reactor thermal hydraulic stability is reported for all cases of core flow bypass. Keywords: Thermal–hydraulics, MTR reactors, Core flow bypass |
| first_indexed | 2024-12-21T20:49:46Z |
| format | Article |
| id | doaj.art-527d0b84f1844d96bbde38b1ef770e1b |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-21T20:49:46Z |
| publishDate | 2019-02-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-527d0b84f1844d96bbde38b1ef770e1b2022-12-21T18:50:44ZengElsevierNuclear Engineering and Technology1738-57332019-02-015115459Thermal hydraulic analysis of core flow bypass in a typical research reactorSaid M.A. Ibrahim0Salah El-Din El-Morshedy1Abdelfatah Abdelmaksoud2Mechanical Engineering Department, Faculty of Engineering, Al-Azhar University, Cairo, EgyptReactors Department, Atomic Energy Authority, Cairo, EgyptReactors Department, Atomic Energy Authority, Cairo, Egypt; Corresponding author.The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe condition with enough safety margins during normal operation and anticipated operational occurrences. In this research, core flow bypass is studied under the conditions of the unavailability of safety systems. As core bypass occurs, the core flow rate is assumed to decrease exponentially with a time constant of 25 s to new steady state values of 20, 40, 60, and 80% of the nominal core flow rate. The thermal hydraulic code PARET is used through these calculations. Reactor thermal hydraulic stability is reported for all cases of core flow bypass. Keywords: Thermal–hydraulics, MTR reactors, Core flow bypasshttp://www.sciencedirect.com/science/article/pii/S1738573318302559 |
| spellingShingle | Said M.A. Ibrahim Salah El-Din El-Morshedy Abdelfatah Abdelmaksoud Thermal hydraulic analysis of core flow bypass in a typical research reactor Nuclear Engineering and Technology |
| title | Thermal hydraulic analysis of core flow bypass in a typical research reactor |
| title_full | Thermal hydraulic analysis of core flow bypass in a typical research reactor |
| title_fullStr | Thermal hydraulic analysis of core flow bypass in a typical research reactor |
| title_full_unstemmed | Thermal hydraulic analysis of core flow bypass in a typical research reactor |
| title_short | Thermal hydraulic analysis of core flow bypass in a typical research reactor |
| title_sort | thermal hydraulic analysis of core flow bypass in a typical research reactor |
| url | http://www.sciencedirect.com/science/article/pii/S1738573318302559 |
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