Fuel rod-grid interaction wear: in-reactor tests

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Description

Wear of the Zircaloy cladding of LWBR irradiation test fuel rods, resulting from relative motion between rod and rod support contacts, is reported. Measured wear depths were small, 0.0 to 2.7 mils, but are important in fuel element behavior assessment because of the local loss of cladding thickness, as well as the effect on grid spring forces that laterally restrain the rods. An empirical wear analysis model, based on out-of-pile tests, is presented. The model was used to calculate the wear on the irradiation test fuel rods attributed to a combination of up-and-down motions resulting from power and pressure/temperature cycling … continued below

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61 pages

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Stackhouse, R. M. November 1, 1979.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 17 times. More information about this report can be viewed below.

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Wear of the Zircaloy cladding of LWBR irradiation test fuel rods, resulting from relative motion between rod and rod support contacts, is reported. Measured wear depths were small, 0.0 to 2.7 mils, but are important in fuel element behavior assessment because of the local loss of cladding thickness, as well as the effect on grid spring forces that laterally restrain the rods. An empirical wear analysis model, based on out-of-pile tests, is presented. The model was used to calculate the wear on the irradiation test fuel rods attributed to a combination of up-and-down motions resulting from power and pressure/temperature cycling of the test reactor, flow-induced vibrations, and assembly handling scratches. The calculated depths are generally deeper than the measured depths.

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61 pages

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Dep. NTIS, PC A04/MF A01.

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Office of Scientific & Technical Information Technical Reports

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  • November 1, 1979

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  • Feb. 10, 2018, 10:06 p.m.

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  • March 3, 2021, 1:19 a.m.

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Stackhouse, R. M. Fuel rod-grid interaction wear: in-reactor tests, report, November 1, 1979; West Mifflin, Pennsylvania. (https://digital.library.unt.edu/ark:/67531/metadc1089030/: accessed December 1, 2023), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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