Bending-induced changes in critical heat flux of nuclear fuel rod in low-pressure system
| dc.contributor.author | Kadavý, Tomáš | |
| dc.contributor.editor | Mašata, David | |
| dc.date.accessioned | 2025-09-22T07:57:02Z | |
| dc.date.available | 2025-09-22T07:57:02Z | |
| dc.date.issued | 2025 | |
| dc.description.abstract-translated | This poster studies the eSect of fuel rod deflection on the critical heat flux (CHF) in a low-pressure water loop. Experiments with various bend deflections and coolant flow rates showed up to a 10% increase in CHF compared to no deflection scenario. Results suggest that bending can delay boiling crisis. Limitations are discussed. | en |
| dc.format | 2 s. | cs |
| dc.identifier.isbn | 978-80-261-1307-2 | |
| dc.identifier.isbn | 978-80-261-1308-9 (printed) | |
| dc.identifier.uri | http://hdl.handle.net/11025/62811 | |
| dc.language.iso | en | en |
| dc.publisher | University of West Bohemia in Pilsen | en |
| dc.rights | © University of West Bohemia in Pilsen | en |
| dc.rights.access | openAccess | en |
| dc.subject | poster | cs |
| dc.subject.translated | poster | en |
| dc.title | Bending-induced changes in critical heat flux of nuclear fuel rod in low-pressure system | en |
| dc.type | konferenční příspěvek | cs |
| dc.type | conferenceObject | en |
| dc.type.status | Peer reviewed | en |
| local.files.count | 2 | * |
| local.files.size | 1407586 | * |
| local.has.files | yes | * |