An overview of heat pipe models in Sockeye

Abstract

Abstract The heat pipe code Sockeye, led by Idaho National Laboratory and funded by the Nuclear Energy Advanced Modeling and Simulation program of the U.S. Department of Energy, provides engineering-scale models of high-temperature heat pipes for use in nuclear microreactors. Sockeye has three heat pipe models, referred to as the Two-Phase model, the Liquid Conduction Vapor Flow (LCVF) model, and the Conduction model. These models are summarized, and various test problems are presented, including verification of the sonic and capillary limits, validation with the SAFE-30 heat pipe module test, and demonstration of multiphysics coupling on a seven-heat-pipe assembly.