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Cunningham, M.E.; Lanning, D.D.
Pacific Northwest Lab., Richland, WA (USA)1984
Pacific Northwest Lab., Richland, WA (USA)1984
AbstractAbstract
[en] Preirradiation characterization data and irradiation data are summarized and postirradiation examination (PIE) data are presented for the six-rod instrumented fuel assembly IFA-527. This assembly was irradiated in the Halden Boiling Water Reactor, Halden, Norway, as part of the US Nuclear Regulatory Commission-sponsored Experimental Support and Verification of Single-Rod Fuel Codes Program. The assembly was irradiated from July 1, 1980, to April 8, 1981, during which time rod-average burnups of approx. 1.0 MWd/kgM were obtained. All six rods had pressure boundary failures prior to removal from the reactor. The PIE was conducted at the Harwell Laboratory of the United Kingdom's Atomic Energy Research Establishment. Examinations were oriented toward discovering the site and cause of rod failure (visual, neutron radiography, leak checking) and the effects of operating an assembly with failed rods (micrography of fuel and cladding). It was concluded that rod failures occurred in the end fittings and not in the cladding. The fuel temperature measurements from this assembly are significant in that they represent a probable maximum temperature response per unit power for BWR rods. These test rods were xenon filled, held at low power, and evidenced no cold gap closure from either fuel relocation or cladding creepdown. Additionally, although these rods operated for several months in a known failed condition, there is no evidence of fuel oxidation or significant cladding hydriding. 13 references, 21 figures, 7 tables
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Jan 1984; 61 p; PNL--4542; Available from NTIS, PC A04/MF A01 - GPO $4.50 as DE84006358
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