2014
DOI: 10.1016/j.nucengdes.2014.09.019
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A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor: A loss of flow accident analysis

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Cited by 7 publications
(5 citation statements)
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References 15 publications
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“…Figure 17 illustrates that the Gnielinski and the Petukhov-Popov correlations clearly overestimate and both Dittus-Boelter correlations underestimate the heat transfer coefficient. Except from the entrance of the channel the Sieder-Tate correlation slightly over-predict and under-predict h. Currently in thermal-hydraulic modeling of the JHR, see (Pegonen et al, 2014a), the Dittus-Boelter correlation is utilized for conservative estimation of h. In light of the present results modified Dittus-Boelter would give a less conservative results and the correlation could be improved when taken into account entrance effect as it is done in Gnielinski correlations. Nevertheless there is an additional project that investigates the improvement possibilities to find a new more reliable correlation.…”
Section: Heat Transfer Coefficient In the Hot Channelmentioning
confidence: 68%
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“…Figure 17 illustrates that the Gnielinski and the Petukhov-Popov correlations clearly overestimate and both Dittus-Boelter correlations underestimate the heat transfer coefficient. Except from the entrance of the channel the Sieder-Tate correlation slightly over-predict and under-predict h. Currently in thermal-hydraulic modeling of the JHR, see (Pegonen et al, 2014a), the Dittus-Boelter correlation is utilized for conservative estimation of h. In light of the present results modified Dittus-Boelter would give a less conservative results and the correlation could be improved when taken into account entrance effect as it is done in Gnielinski correlations. Nevertheless there is an additional project that investigates the improvement possibilities to find a new more reliable correlation.…”
Section: Heat Transfer Coefficient In the Hot Channelmentioning
confidence: 68%
“…• The CEA 36 assembly JHR core reference power is 108.77 MW (Pegonen et al, 2014a), from which 5.145 MW is the total power of the hot fuel element and 0.264 MW is the power in the water, in the hot channel, originating from neutron moderation and gamma heating. In here it is assumed that the hot assembly and the water in it have the power with the factor 1.79 compared to the mean values.…”
Section: Modeling Assumptionsmentioning
confidence: 99%
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