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首页> 美国政府科技报告 >Fuel Rod-Grid Interaction Wear: In-Reactor Tests (LWBR Development Program)
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Fuel Rod-Grid Interaction Wear: In-Reactor Tests (LWBR Development Program)

机译：燃料棒 - 网格相互作用磨损：反应堆内试验（LWBR开发计划）

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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. (ERA citation 05:017710)

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