Open AccessProbability of pipe failure in the reactor coolant loops of Westinghouse PWR Plants. Volume 1. Summary report
Author(s) -
G.S. Holman,
ChenLin Chou
Publication year - 1985
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/5655355
Subject(s) - piping , pressurized water reactor , coolant , nuclear engineering , transuranium element , nuclear power plant , fragility , nuclear reactor , engineering , environmental science , nuclear physics , radioactive waste , waste management , physics , mechanical engineering , thermodynamics
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