CORSOR user's manual

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Abstract
The CORSOR code simulates the release of fission products and structural materials from a reactor core during the in-vessel period of a severe accident in a light water reactor. The code is a simple, empirically based treatment of release and does not treat detailed mechanisms for release from high temperature fuel. The first-order release rate coefficients for the species considered are presented, the input requirements of the code are described, and an example input and output stream is supplied in an appendix.

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