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...
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| 主要な著者: | , , |
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| フォーマット: | Artigo |
| 言語: | Inglês |
| 出版事項: |
Elsevier
2019-02-01
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| シリーズ: | Nuclear Engineering and Technology |
| オンライン･アクセス: | http://www.sciencedirect.com/science/article/pii/S1738573318302559 |
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