Open AccessThe DF-4 fuel damage experiment in ACRR (Annual Core Research Reactor) with a BWR (Boiling Water Reactor) control blade and channel box
Author(s) -
Randall O. Gauntt,
R.D. Gasser,
L.J. Ott
Publication year - 1989
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/5101359
Subject(s) - boiling water reactor , nuclear engineering , bundle , nuclear fission product , thermocouple , cladding (metalworking) , nuclear reactor core , materials science , corium , boiling , zirconium alloy , fission products , natural circulation , light water reactor , heat transfer , composite material , engineering , mechanics , thermodynamics , physics , alloy
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