Diffusion of radioactive gases through power reactor graphite
Abstract
Results of a study concerned with the problem of retarding the diffusion of fission products through unclad graphite fuel elements are presented. The pertinent parameters are pointed out, and their relations with the properties of graphite and gas coolants are considered. The effects of parameter variation on the concentration in the reactor primary system and the fission-product diffusion rate into the primary system are also examined. (J.R.D.)
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