1 Bethel Valley Road, P.O. Box 2008, Mail Stop 608
Room B-106, Building 5700
Oak Ridge, TN 37831
United States
Government of the United States of America - Oak Ridge National Laboratory
liquid-fueled molten salt reactor, depletion model, diversion scenario, safeguards
SCALE, molten salt reactor, depletion, fuel cycle, nuclide removal, continuous feed, MSRE
Molten Salt Breeder Reactor, facility dose, Shift, delayed neutron precursors, Hybrid Monte Carlo/deterministic methods