1. Toward a Mechanistic Source Term in Advanced Reactors: Characterization of Radionuclide Transport and Retention in a Sodium Cooled Fast Reactor;Brunett,2016
2. Next generation nuclear plant phenomena identification and ranking tables (PIRTs) Volume 3: fission-product transport and dose PIRTs;Morris,2008
3. Nuclear graphite for high temperature gas-cooled reactors;Zhou;New Carbon Mater.,2017
4. Plate-out of fission products and its effect on maintenance and repair;Iniotakis;Nucl. Eng. Des.,1984
5. Fuel performance and Fission product behavior in gas-cooled reactors;Tech. Rep.,1997