Abstract
Spacer grids have been found to enhance downstream convective heat transfer and to strongly influence droplet size distributions through early spacer grid rewet and droplet breakup. Existing models for enhancement of heat transfer and droplet breakup, however, do not appear to accurately account for these interactions between the coolant and the spacer grid. Data from two series of rod bundle heat transfer tests, low injection rate forced reflood tests, and droplet injection tests are presented in this paper to describe the effects of the spacer grids during dispersed flow film boiling. Heat transfer downstream of the spacer grids is clearly enhanced by the presence of the droplets, while the downstream droplet size was found to depend on the condition of the spacer grid: dry or wetted. Results of this study demonstrate the need to adequately account for the separate modes of dry and wet spacer grid heat transfer enhancement in predicting the thermal-hydraulic behavior during reflood transients.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 336-358 |
| Number of pages | 23 |
| Journal | Nuclear Technology |
| Volume | 190 |
| Issue number | 3 |
| DOIs | |
| State | Published - Jun 1 2015 |
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All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Condensed Matter Physics
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Experimental studies of spacer grid thermal hydraulics in the dispersed flow film boiling regime. / Riley, Michael; Mohanta, L.; Cheung, Fan-bill B.; Bajorek, S. M.; Tien, K.; Hoxie, C. L.
In: Nuclear Technology, Vol. 190, No. 3, 01.06.2015, p. 336-358.Research output: Contribution to journal › Article
TY - JOUR
T1 - Experimental studies of spacer grid thermal hydraulics in the dispersed flow film boiling regime
AU - Riley, Michael
AU - Mohanta, L.
AU - Cheung, Fan-bill B.
AU - Bajorek, S. M.
AU - Tien, K.
AU - Hoxie, C. L.
PY - 2015/6/1
Y1 - 2015/6/1
N2 - Spacer grids have been found to enhance downstream convective heat transfer and to strongly influence droplet size distributions through early spacer grid rewet and droplet breakup. Existing models for enhancement of heat transfer and droplet breakup, however, do not appear to accurately account for these interactions between the coolant and the spacer grid. Data from two series of rod bundle heat transfer tests, low injection rate forced reflood tests, and droplet injection tests are presented in this paper to describe the effects of the spacer grids during dispersed flow film boiling. Heat transfer downstream of the spacer grids is clearly enhanced by the presence of the droplets, while the downstream droplet size was found to depend on the condition of the spacer grid: dry or wetted. Results of this study demonstrate the need to adequately account for the separate modes of dry and wet spacer grid heat transfer enhancement in predicting the thermal-hydraulic behavior during reflood transients.
AB - Spacer grids have been found to enhance downstream convective heat transfer and to strongly influence droplet size distributions through early spacer grid rewet and droplet breakup. Existing models for enhancement of heat transfer and droplet breakup, however, do not appear to accurately account for these interactions between the coolant and the spacer grid. Data from two series of rod bundle heat transfer tests, low injection rate forced reflood tests, and droplet injection tests are presented in this paper to describe the effects of the spacer grids during dispersed flow film boiling. Heat transfer downstream of the spacer grids is clearly enhanced by the presence of the droplets, while the downstream droplet size was found to depend on the condition of the spacer grid: dry or wetted. Results of this study demonstrate the need to adequately account for the separate modes of dry and wet spacer grid heat transfer enhancement in predicting the thermal-hydraulic behavior during reflood transients.
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U2 - 10.13182/NT14-80
DO - 10.13182/NT14-80
M3 - Article
AN - SCOPUS:84937959194
VL - 190
SP - 336
EP - 358
JO - Nuclear Technology
JF - Nuclear Technology
SN - 0029-5450
IS - 3
ER -