
Design criteria for phase II dummy hydraulic core for containment systems experiment reactor simulator
Author(s) -
Charles H. Henager
Publication year - 1966
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/7345885
Subject(s) - thermal hydraulics , baffle , core (optical fiber) , nuclear engineering , mockup , nuclear reactor core , boiler blowdown , control rod , simulation , engineering , mechanical engineering , mechanics , heat transfer , physics , telecommunications , inlet