CALCULATION OF DESIGN-BASIS ACCIDENTS LOSS OF COOLANT CIRCULATION FOR THE IRT MIFI REACTOR

摘要

The results of calculations of emergency situations for the IRT MIFI [Moscow Engineering Physics Institute] reactor with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel cores based on the alloy U-9%Mo in an aluminum matrix with 19.7% enrichment are presented. The transient processes due to disruption of coolant circulation during the execution of safety functions are examined. The PARET 7.5 software is used to calculate the transient processes. Special attention is focused on taking account of emergency protection engagement algorithms and the characteristic features of the devices monitoring the thermohydraulic parameters of the reactor in setting the initial data for the calculation of transient processes.