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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports Under Various Autoclave and Hydraulic Loop Endurance Test Conditions
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Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports Under Various Autoclave and Hydraulic Loop Endurance Test Conditions

机译：Zircaloy-4，OPTIN™和ZIRLO™燃料棒和格栅支架在各种高压釜和液压回路耐久性测试条件下的微动磨损行为

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摘要

High fuel duty, eighteen-month and longer cycle lengths, and higher burnups have put increased demands on pressurized water reactor (PWR) fuel during recent years. As a result of these demanding operating conditions, the fretting-wear performance of PWR fuel rods against structural grid supports is being challenged. To understand the in-reactor fretting-wear performance of PWR fuel, Westinghouse Electric Company (W) and Atomic Energy of Canada Limited (AECL) have performed investigations to study the fretting-wear behavior of zirconium alloy nuclear fuel rods and grid supports. Experimental work was carried out at the AECL Chalk River Laboratories (Canada) in autoclave impact fretting-wear test machines and at the W Columbia, South Carolina (USA) plant in the Westinghouse -Vibration Investigation Pressure-Drop Experimental Research (VIPER) hydraulic test loop. Autoclave impact fretting-wear tests were conducted for several grid-support/fuel-rod designs using either ZIRLO™, Zircaloy-4, and/or OPTIN™ materials. Rod-to-grid relative displacements and contact forces were measured throughout each test. The wear volumes of each fret mark on the fuel rod specimens were measured via surface profilometry at the end of each test. From these wear volumes, wear rates and wear coefficients for the fuel rod in contact with either springs or dimples were determined. The VIPER loop is used for full-scale nuclear fuel assembly vibration and wear testing. Endurance tests were performed with severe flow conditions to induce fuel fretting-wear for different grid support and assembly designs using either all ZIRLO™ or all Zircaloy-4 materials. The wear volumes of the most severe fret marks on the fuel rods were measured via surface profilometry at the end of each test. From the profilometry of each fret mark, and using the fretting-wear coefficient derived from autoclave wear tests, the available energy (i.e., work-rate) to cause the fretting-wear damage was determined. Fretting-wear scars on ZIRLO™, Zircaloy-4, and/or OPTIN™ fuel rods from the autoclave impact fretting-wear tests and the VIPER hydraulic tests were examined using scanning electron microscopy (SEM) to compare the fretting-wear mechanisms for different grid-support designs. Fretting-wear mechanisms from both types of tests were shown to be comparable and related to the grid-support design. For a given material (i.e., ZIRLO™, Zircaloy-4, or OPTIN™) under similar test conditions, there was no difference in the fretting-wear performance.
机译：近年来，高燃料负荷，十八个月和更长的周期长度以及更高的燃耗对压水堆（PWR）燃料提出了更高的要求。由于这些苛刻的运行条件，PWR燃料棒对结构格栅的微动磨损性能受到了挑战。为了了解PWR燃料的反应堆内部微动磨损性能，西屋电气公司（W）和加拿大原子能有限公司（AECL）进行了调查，以研究锆合金核燃料棒和电网支架的微动磨损行为。在AECL粉笔河实验室（加拿大）的高压釜冲击微动磨损试验机上以及在西屋（Southinghouse）的南卡罗来纳州W哥伦比亚（美国）工厂进行了试验工作-振动研究压降试验研究（VIPER）液压试验环。使用ZIRLO™，Zircaloy-4和/或OPTIN™材料对几种网格支撑/燃料棒设计进行了高压釜冲击微动磨损测试。在每个测试过程中都测量了杆对格的相对位移和接触力。在每次测试结束时，通过表面轮廓仪测量燃油棒样品上每个品格痕迹的磨损量。从这些磨损量中，确定了与弹簧或凹窝接触的燃料棒的磨损率和磨损系数。 VIPER回路用于全面的核燃料组件振动和磨损测试。使用所有ZIRLO™或所有Zircaloy-4材料，在苛刻的流动条件下进行了耐久测试，以引起燃料在不同的支架和组件设计中的磨损。在每次测试结束时，通过表面轮廓仪测量燃油棒上最严重的磨损痕迹的磨损量。从每个品格痕迹的轮廓测定法，并使用从高压釜磨损试验得出的微动磨损系数，确定引起微动磨损的可用能量（即工作率）。使用扫描电子显微镜（SEM）对高压釜冲击微动磨损试验和VIPER液压试验中的ZIRLO™，Zircaloy-4和/或OPTIN™燃料棒上的微动磨损痕迹进行了比较，以比较不同情况下的微动磨损机理网格支持设计。两种测试的微动磨损机理都具有可比性，并且与网格支撑设计有关。对于在相似测试条件下的给定材料（即ZIRLO™，Zircaloy-4或OPTIN™），微动磨损性能没有差异。

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