On line system for power generation of the IPR-R1 TRIGA reactor by thermal methods

Abstract

The IPR-R1 research reactor es a TRIGA Mark I type reactor. The IPR-R1 ia a pool reactor, and the fuel elements at the core are cooled by water natural convection. The heat removal capacity of this process is great enough for safety reasons at the current maximum 250 kW power levels of the reactor. However, a heat removal system is provided for removing heat from the reactorpool water. Power monitoring of nuclear reactors is always done by means of neutronics instruments. Inthe IPR-R1 the power is measured by four nuclear channels. This work presents the results and methodology for monitoring the power of this reactor by thermal processes. Three improved methods for thermal measuring chennels are described using the fuel element temperature and the steady-state energy balance of the primary and secondary cooling loops.