On the natural convection cooling of advanced reactor vessels

K. H. Haddad, Fan-bill B. Cheung, D. Y. Sohn

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The process of turbulent natural convection in a vertical channel formed by two parallel plates maintained at constant temperatures is studied numerically. The objective is to obtain basic information needed to predict the rate of natural convection cooling of advanced passive reactor vessels under abnormal operating conditions. A low-Reynolds-number turbulence model is employed in the problem formulation and the governing system is solved by an implicit finite-difference method. The development of flow and heat transfer in the channel is investigated for both the symmetric and asymmetric heating cases. Numerical results are obtained showing the effects of various parameters on the pressure variation and heat transfer performance of the system. Based on the characteristics of the heat flux variation along the channel, the concept of critical channel length is developed which leads to the highest heat transfer per unit length of the channel. Comparison of the present results is made with those obtained under constant-wall-heat-flux conditions.

Original languageEnglish (US)
Title of host publicationNuclear Reactor Thermal-Hydraulics
PublisherPubl by ASME
Pages7-16
Number of pages10
ISBN (Print)079180884X
Publication statusPublished - Dec 1 1991
EventWinter Annual Meeting of the American Society of Mechanical Engineers - Atlanta, GA, USA
Duration: Dec 1 1991Dec 6 1991

Publication series

NameAmerican Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD
Volume190
ISSN (Print)0272-5673

Other

OtherWinter Annual Meeting of the American Society of Mechanical Engineers
CityAtlanta, GA, USA
Period12/1/9112/6/91

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All Science Journal Classification (ASJC) codes

  • Mechanical Engineering
  • Fluid Flow and Transfer Processes

Cite this

Haddad, K. H., Cheung, F. B., & Sohn, D. Y. (1991). On the natural convection cooling of advanced reactor vessels. In Nuclear Reactor Thermal-Hydraulics (pp. 7-16). (American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD; Vol. 190). Publ by ASME.