Abonnement à la biblothèque: Guest
Multiphase Science and Technology

Publication de 4  numéros par an

ISSN Imprimer: 0276-1459

ISSN En ligne: 1943-6181

SJR: 0.144 SNIP: 0.256 CiteScore™:: 1.1 H-Index: 24

Indexed in

EFFECT OF THERMAL−HYDRAULIC PARAMETERS ON ENTROPY GENERATION IN A BOILING CHANNEL

Volume 26, Numéro 4, 2014, pp. 287-303
DOI: 10.1615/MultScienTechn.v26.i4.20
Get accessGet access

RÉSUMÉ

In this study, the optimization of local entropy generation for water/vapor-saturated two-phase flow in a vertical channel is conducted using entropy generation minimization. The contributions of heat transfer and pressure drop to entropy generation is considered. Appropriate models for estimating heat transfer and pressure drop in a boiling channel are applied. The drift flux model is used to predict the void fraction along the boiling channel. The effect of influential thermal-hydraulic parameters such as the inlet quality, induced power, power distribution profile, channel hydraulic diameter, and inlet mass flux on channel entropy generation is presented. The optimum channel hydraulic diameter is predicted as a function of the system pressure. Also, an appropriate critical heat flux model is applied to the boiling channel to insure safety margin evaluation. It is found that an increase in system pressure decreases the optimized channel hydraulic diameter. For each flow condition, there is a mass flux at which the entropy generation rate is maximized. It was also observed that the channel power distribution profile has an important effect on the entropy generation of a boiling channel. Uniform power distribution is preferred for both minimum entropy generation and a wider margin of safety.

CITÉ PAR
  1. Talebi S., Valoujerdi M. M., Thermal–hydraulic performance analysis of a subchannel with square and triangle fuel rod arrangements using the entropy generation approach, Nuclear Science and Techniques, 28, 10, 2017. Crossref

  2. Valujerdi M.M., Talebi S., Entropy generation study for a supercritical water reactor (SCWR), Progress in Nuclear Energy, 118, 2020. Crossref

Portail numérique Bibliothèque numérique eBooks Revues Références et comptes rendus Collections Prix et politiques d'abonnement Begell House Contactez-nous Language English 中文 Русский Português German French Spain