Assessment and improvements of thermal-hydraulic correlations and methods for the analysis of the Jules Horowitz Reactor
Doktorsavhandling, 2017
Flow instability
Uncertainty
Narrow channels
Jules Horowitz Reactor
Safety analysis
Critical heat flux
Thermal-hydraulic correlations
Heat transfer
Best-Estimate
Material Testing Reactor
Författare
Alberto Ghione
Chalmers, Fysik, Subatomär fysik och plasmafysik
Assessment of Critical Heat Flux correlations in narrow rectangular channels
Proceedings of the 11th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, Oct. 9-13 2016,;(2016)
Paper i proceeding
Assessment of thermal–hydraulic correlations for narrow rectangular channels with high heat flux and coolant velocity
International Journal of Heat and Mass Transfer,;Vol. 99(2016)p. 344-356
Artikel i vetenskaplig tidskrift
Criteria for onset of flow instability in heated vertical narrow rectangular channels at low pressure: an assessment study
International Journal of Heat and Mass Transfer,;Vol. 105(2017)p. 464-478
Artikel i vetenskaplig tidskrift
Ghione A., Noel B., Vinai P., Demazière C., Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor
Although the JHR core is small, the performances are rather extreme. In fact the experiments require large neutron fluxes to develop irradiation effects typical of nuclear power plants, over short time periods. Therefore significant heat fluxes are generated in the core, and the cooling is achieved with water at high velocity through narrow channels.
When operating a nuclear reactor, a sufficient level of safety have to be assured in order to minimize the potential for radioactivity releases to the environment. The safety analysis relies on computational methods developed for the simulation of the system behavior. In particular, a thermal-hydraulic modeling is needed to study the cooling of the reactor under a variety of scenarios.
In this doctoral thesis possible improvements of the thermal-hydraulic modeling of the JHR are proposed. From the investigation of proper experiments, heat transfer correlations and criteria of flow instability and boiling crisis are recommended for the specific case of the JHR. Moreover, a more realistic approach is tested for the safety analysis of the JHR, where the correlations optimized for the reactor are combined with an evaluation of the input and modeling uncertainties.
Ämneskategorier
Materialteknik
Subatomär fysik
ISBN
978-91-7597-520-7
Doktorsavhandlingar vid Chalmers tekniska högskola. Ny serie: 4201
Utgivare
Chalmers
PJ lecture hall, Origo, Kemigården 1, Chalmers
Opponent: Dr. Dominique Bestion, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Grenoble, France