Authors: Ashok K. Satapathy
Addresses: Department of Mechanical Engineering, National Institute of Technology, Rourkela 769008, Orissa, India
Abstract: This review deals with conduction-controlled rewetting analysis for water-cooled nuclear reactors following a hypothetical Loss-of-Coolant Accident (LOCA). The first part of the survey deals with analytical solutions for various rewetting models. This contains the solution for one- and two-dimensional models, rewetting models with and without precursory cooling, rewetting models for two- and three-region heat transfers and also rewetting models with boundary heat flux. The second part of the survey deals with numerical solutions for quasi-steady as well as transient heat conduction models for rewetting.
Keywords: loss-of-coolant accidents; LOCA; boiling; rewetting; quenching; reflooding; water-cooled nuclear reactors; nuclear accidents; nuclear energy; nuclear power; modelling; heat transfer; boundary heat flux; transient heat conduction.
International Journal of Nuclear Energy Science and Technology, 2010 Vol.5 No.2, pp.171 - 188
Available online: 21 Dec 2009 *Full-text access for editors Access for subscribers Purchase this article Comment on this article