Open AccessHigh Fidelity Forward Model Development for Nuclear Reactor Spent Fuel Technical Nuclear Forensics
Author(s) -
Matthew R. Sternat
Publication year - 2015
Language(s) - English
Resource type - Reports
DOI - 10.2172/1494622
Subject(s) - burnup , nuclear engineering , spent nuclear fuel , uranium , research reactor , computer science , neutron flux , environmental science , neutron , engineering , nuclear physics , physics
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