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Conference Article: Fission product release characteristics of the experimental VHTR core

Abstract

Fission product release characteristics of the experimental VHTR core is analyzed. The reactor is equipped with a loop type plant for process heat application test, and is designed to generate high temperature coolant of 950 deg C. Plateout activities and circulating activities in the primary cooling system are calculated for various core conditions, and operator dose in maintenance work and offsite public dose during normal operation of the reactor are evaluated. The result shows that fission product retention in the graphite matrix and the fuel sleeve is degraded at high temperature condition in the VHTR core, and that high radiation dose in the maintenance work is caused by cesium isotopes, and it is also indicated that development of coated fuel particle with higher performance or any means for plateout fission product will be required for a HTR plant with higher outlet temperature.

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Reference:

Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment Moscow (Russian Federation) 18-21 Oct 1983

International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria); State Committee on the Utilisation of Atomic Energy of the USSR, Moscow (Russian Federation)

IWGGCR--8, pp:255-263