The research and development effort for the next generation of nuclear power
stations is being coordinated by the Generation IV International Forum (GIF). The
supercritical water reactor (SCWR) is one of the six reactor technologies currently
being pursued by the GIF. The unique nature of supercritical water necessitates
further examination of its heat transfer regimes. The GIF SCWR blind
computational benchmark exercise is focused on furthering the understanding of
the heat transfer to supercritical water as well as its prediction.
A methodology for computational fluid dynamics (CFD) simulations using
STAR-CCM+ 9.02.005 has been developed for submission to the GIF SCWR
computational benchmark exercise. The experiments of the GIF SCWR
computational benchmark exercise were those conducted by the Japan Atomic
Energy Agency (JAEA). They are of supercritical water flowing upward in a 7
rod bundle. Of the three experimental cases there are (i) an isothermal case, (ii) a
low enthalpy, low heat flux case and (iii) a high enthalpy, high heat flux case. A
separate effects study has been undertaken and the SST turbulence model has
been chosen to model each of the three experiments. A near wall treatment that ensures a y+<0.09 has been used for both of the heated cases and a near wall
treatment that ensures a y+<0.53 has been used for the isothermal case. This computational approach was determined to be the optimal choice which balances
solution accuracy with computation time.
Final simulation results are presented in advance of the release of the
experimental results in June 2014. / Thesis / Master of Applied Science (MASc)
| Identifer | oai:union.ndltd.org:mcmaster.ca/oai:macsphere.mcmaster.ca:11375/15392 |
| Date | 06 1900 |
| Creators | McClure, Darryl |
| Contributors | Novog, David, Engineering Physics |
| Source Sets | McMaster University |
| Language | English |
| Detected Language | English |
| Type | Thesis |
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