In this paper, we present a numerical analysis of the effect of different heat transfer correlations on the prediction of the cladding wall temperature in a supercritical water reactor at nominal operating conditions. The neutronics process with temperature feedback effects, the heat transfer in the fuel rod, and the thermal-hydraulics in the core were simulated with a three-pass core design. | Effect of heat transfer correlations on the fuel temperature prediction of SCWRs EPJ Nuclear Sci. Technol. 2 35 2016 Nuclear Sciences . Espinosa-Martínez et al. published by EDP Sciences 2016 amp Technologies DOI epjn 2016030 Available online at http REGULAR ARTICLE Effect of heat transfer correlations on the fuel temperature prediction of SCWRs Erick-Gilberto Espinosa-Martínez1 Cecilia Martin-del-Campo1 Juan-Luis François1 and Gilberto Espinosa-Paredes2 3 1 Departamento de Sistemas Energéticos Facultad de Ingeniería Universidad Nacional Autónoma de México . 62550 Jiutepec Mor. Mexico 2 Área de Ingeniería en Recursos Energéticos Universidad Autónoma Metropolitana-Iztapalapa . 09340 México . Mexico 3 Sabbatical leave at the Facultad de Ingeniería of the Universidad Nacional Autónoma de México through the Programa de Estancias Sabáticas del CONACyT México . Mexico Received 9 June 2015 Received in final form 17 May 2016 Accepted 20 July 2016 Abstract. In this paper we present a numerical analysis of the effect of different heat transfer correlations on the prediction of the cladding wall temperature in a supercritical water reactor at nominal operating conditions. The neutronics process with temperature feedback effects the heat transfer in the fuel rod and the thermal- hydraulics in the core were simulated with a three-pass core design. 1 Introduction channel. The first pass called evaporator is located in the center of the core. In this region the moderator water flows The super critical water reactor SCWR is one of the most downward in gaps between assembly boxes and inside the promising and innovative designs selected by the Genera- moderator tubes. The moderator water heated-up through tion IV International Forum. This is a very high-pressure its path downward to the lower plenum is mixed with the water-cooled reactor which will operate at conditions coolant coming from the downcomer reaching an inlet above the thermodynamic .
