Open AccessDetailed heat load calculations at the beginning, middle, and end of cycle for the conceptual design of the Advanced Neutron Source Reactor
Author(s) -
C.A. Wemple,
Bruce G. Schnitzler
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/1329239
Subject(s) - oak ridge national laboratory , conceptual design , nuclear engineering , research reactor , nuclear fuel cycle , neutron , neutron flux , reactor design , nuclear reactor core , nuclear physics , engineering , process engineering , environmental science , mechanical engineering , physics , fuel cycle