TY - GEN
T1 - Application of RPI model
T2 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
AU - Zhang, Rui
AU - Zhang, Wenwen
AU - Cong, Tenglong
AU - Tian, Wenxi
AU - Su, G. H.
AU - Qiu, Suizheng
N1 - Publisher Copyright:
© Copyright (2015) by American Nuclcar Society All rights reserved.
PY - 2015
Y1 - 2015
N2 - In this work, the RPI wall boiling model is used to predict the subcooled boiling for water and Freon and the CHF for water in vertical pipes. The heat flux is divided into four parts in the RPI wall boiling model, i.e., evaporation heat flux, convective heat flux and quench heat flux for liquid phase and the convective heat flux for vapor phase. The wetted fraction of each phase is correlated by an empirical correlation. In the subcooled boiling applications, the calculated wall temperature, fluid temperature and void fraction distribution are compared with the experiment data. In the CHF applications, the predicted CHFs are compared with experimental values. The deviation of the CHF values are less than 15% when compared to experiment data, which is much better than empirical correlations. Besides, the parameter analysis is performed to investigate the effects of L/D, D, inlet subcooling and pressure on CHF.
AB - In this work, the RPI wall boiling model is used to predict the subcooled boiling for water and Freon and the CHF for water in vertical pipes. The heat flux is divided into four parts in the RPI wall boiling model, i.e., evaporation heat flux, convective heat flux and quench heat flux for liquid phase and the convective heat flux for vapor phase. The wetted fraction of each phase is correlated by an empirical correlation. In the subcooled boiling applications, the calculated wall temperature, fluid temperature and void fraction distribution are compared with the experiment data. In the CHF applications, the predicted CHFs are compared with experimental values. The deviation of the CHF values are less than 15% when compared to experiment data, which is much better than empirical correlations. Besides, the parameter analysis is performed to investigate the effects of L/D, D, inlet subcooling and pressure on CHF.
KW - CHF
KW - RPI
KW - Subcooled boiling
UR - https://www.scopus.com/pages/publications/84962679714
M3 - 会议稿件
AN - SCOPUS:84962679714
T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
SP - 2658
EP - 2672
BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PB - American Nuclear Society
Y2 - 30 August 2015 through 4 September 2015
ER -