Flow blockage analysis of a channel in a typical material test reactor core Original Research Article

The course of the partial and total blockage of a channel in the IAEA 10 MW MTR pool type research reactor core (IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.) without scram is investigated. The analysis is performed with the best estimate code RELAP5/MOD3.3. The interaction of the obstructed channel and its adjacent channels has been taken account of. Results indicated that even when the flow channel has been totally blocked, there is still no boiling occurrence, and the fuel temperature is low enough to maintain its integrity. This work indicates that the consideration of the conjugate heat transfer in the obstructed channel during this transient is very important.