ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature
An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection (HPI) system in a pressurized water reactor (PW...
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| Format: | Article |
| Language: | English |
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Elsevier
2018-12-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573318301542 |