Open AccessDevelopment of a fuel-rod simulator and small-diameter thermocouples for high-temperature, high-heat-flux tests in the Gas-Cooled Fast Reactor Core Flow Test Loop
Author(s) -
R.W. McCulloch,
R.E. MacPherson
Publication year - 1983
Language(s) - English
Resource type - Reports
DOI - 10.2172/6213539
Subject(s) - thermocouple , cladding (metalworking) , nuclear engineering , materials science , core (optical fiber) , transient (computer programming) , nuclear reactor core , temperature measurement , mechanics , composite material , thermodynamics , engineering , physics , computer science , operating system
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