Annotated bibliography on in-vessel retention processes

Wright, etal.. Primary System Fission Product Release and Transport - A 

State-of-the-Art Report to the Committee on the Safety of Nuclear Installations, 

NUREG/CR-6193, NEA/CSNI/R(94)2, ORNL/TM-12681, Oak Ridge National Laboratory, Oak Ridge, TN, June 1994. 

This report provides a comprehensive survey of experimental data and models available to predict the retention of radionuclides within the reactor coolant system during severe accidents. 

Denning etal.. Radionuclide Release Calculations for Selected Severe Accident 

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