Thermal-hydraulic feasibility analysis on uprating the HTR-PM

In order to meet energy demand in China, the high temperature gas-cooled reactor-pebble-bed module (HTR-PM) is being developed. It adopts a two-zone core, in which graphite balls are loaded in the central zone and the outer part is fuel ball zone, and couple with a steam cycle. Outer diameter of the reactor core is 4.0 m and height of the core is 9.43 m. The helium inlet and outlet temperature are 250 and 750 degrees C, respectively. The reactor thermal power is 380 MW. Preliminary studies show that the HTR-PM is feasible technologically and economically. In order to increase the reactor thermal power of the HTR-PM, some efforts have been made. These include increasing the height of reactor core, optimizing the thickness of fuel zone and better selection of the scheme of central graphite zone, etc. Basic design concepts and thermal-hydraulic parameters of the HTR-PM are given. Measures to increase the thermal power are introduced. Thermal-hydraulic analysis results are presented. The results show that, from the viewpoint of thermal-hydraulics, it is possible to increase the reactor power. (c) 2006 Elsevier B.V. All rights reserved.