A large set of experimental data, obtained in Russia, was analyzed and a new
heat-transfer correlation for supercritical water was developed. This
experimental dataset was obtained within conditions similar to those for proposed
SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, this new
correlation, for forced convective heat transfer in the normal heat-transfer regime,
can be used for preliminary heat-transfer calculations in SCWR fuel channels. It
has demonstrated a good fit for Heat Transfer Coefficient (HTC) values (±25%)
and for wall temperature calculations (±15) for the analyzed dataset. This
correlation can be used for supercritical water heat exchangers linked to indirectcycle
concepts and the co-generation of hydrogen, for future comparisons with
other independent datasets, with bundle data, as the reference case, for the
verification of computer codes for SCWR core thermalhydraulics and for the
verification of scaling parameters between water and modeling fluids. / UOIT
| Identifer | oai:union.ndltd.org:LACETR/oai:collectionscanada.gc.ca:OOSHDU.10155/84 |
| Date | 01 December 2009 |
| Creators | Mokry, Sarah |
| Contributors | Pioro, Igor |
| Source Sets | Library and Archives Canada ETDs Repository / Centre d'archives des thèses électroniques de Bibliothèque et Archives Canada |
| Language | English |
| Detected Language | English |
| Type | Thesis |
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