Open AccessElectrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]
Author(s) -
J.O. Barner,
D.E. Fitzsimmons
Publication year - 1985
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/6021014
Subject(s) - cladding (metalworking) , pellet , nuclear engineering , oak ridge national laboratory , pressurized water reactor , rod , zirconium alloy , materials science , light water reactor , composite material , nuclear physics , zirconium , engineering , metallurgy , physics , alternative medicine , pathology , medicine