Heat-transfer Analysis of SCW to SCW Double-pipe Heat Exchanger for Indirect-cycle SCW NPPS

Abstract

This paper presents the heat transfer analysis of an intermediate Heat eXchanger (HX) design for indirect-cycle concepts of Pressure-Tube (PT) and Pressure-Vessel (PV) SuperCritical Water- cooled Reactors (SCWRs). Thermodynamic configurations with an intermediate HX give a possibility to have a single-reheat option for PT and PV SCWRs without introducing steam- reheat channels into a reactor. Similar to the current CANDU and Pressurized Water Reactor (PWR) Nuclear Power Plants (NPPs), steam generators separate the primary loop from the secondary loop. In this way, the primary loop can be completely enclosed in a reactor containment building.