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Effects of burnup on fuel failure. Power burst tests on fuel rods with 13,000 and 32,000 MWd/MTU burnup
Author(s) -
Richard W. Miller
Publication year - 1976
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4054719
Subject(s) - burnup , nuclear engineering , rod , interim , criticality , shut down , nuclear reactor core , environmental science , pressurized water reactor , core (optical fiber) , materials science , nuclear physics , engineering , physics , medicine , political science , law , alternative medicine , pathology , composite material
Results are presented from preliminary tests designed to investigate the behavior of preirradiated fuel rods under reactivity initiated accident (RIA) conditions. The tests were conducted in 1970 as part of the SPERT/Capsule Driver Core (CDC) program. The report was intended to be published in a series of Idaho Nuclear Corporation Interim Technical Reports (IN-ITRs); however, the CDC program was terminated before the report could be released. In September 1975, the Nuclear Regulatory Commission concluded that the data contained in the report could be a valuable reference in planning future water reactor safety program tests and requested its release

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