Improvement of the Transcritical Heat Transfer Look-up Table by Including separate Effects

点击翻译按钮获取中文摘要

Current reactor safety codes are designed to assess the fuel thermal behaviour under normal and accident conditions of CANDU reactors. These safety codes may have been modified to predict fuel thermal behaviour at conditions relevant to supercritical water-cooled reactors (SCWR) but for an idealized geometry. The results of the present Phase II research proposal will provide an improved heat transfer prediction method to be used in reactor safety codes in order to make them more applicable to various normal and accident SCWR conditions and applicable for a more realistic flow geometry, i.e. by considering (i) the flow direction effect, (ii) the effect of flow geometry (by comparing the supercritical heat transfer (SCHT) in tubular geometries vs. bundle geometries), (iii) the presence of flow obstructions, e.g., introduced by fuel rod spacers, and (iv) transient flow conditions, with time dependent pressure, mass flow and/or heat flux. This will enable the reactor safety analysts to better assess the impact of the previously mentioned separate effects on the sheath temperature behaviour during normal operating and accident conditions.