Thermophysical method for determining energy parameters of model fuel assemblies in impulse tests on pulsed uranium-graphite reactor

Abstract

The paper introduces the computational-experimental technique for controlling energy release in fuel assemblies at their testing in central experimental channel of pulse research reactor. The results of the technique approbation in the course of the test sequence with the experimental device are introduced. The device is intended for studying the behavior of model fuel assemblies of the reactor unit of VVER-1000 type under conditions modeling the final accident stage with loss of coolant.

Keywords

• pulsed research nuclear reactor
• nuclear fuel
• test
• heat emission
• monitoring