Advanced Course in Heat Transfer in Nuclear Reactor Safety
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf
ISBN Print: 978-0-89116-223-0
1.4 Overview of Mathematical Models for Nuclear Reactor Safety Heat Transfer Computer Codes and Experiments
pages 111-132
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.50
摘要
The state of the art and the problems in the field of the reactor safety calculations are considered, primarily on the USSR experience. The results of some theoretical and experimental investigations of unsteady processes of heat and mass transfer are presented. Some constitutive equations for system modeling are discussed.