The Occurrence of Wear Marks on Fast Reactor Fuel
Pin Cladding
期刊名称： Journal of Nuclear Science & Technology
作者： OTSUBO, Akira,OKADA, Toshio,TAKAHASHI, Nobutomo,SATO,
Kazujirou,HATTORI, Naozou
年份： 1999年
reactor technology
期号： 第6期
关键词： wear mark; contact mark; fuel pins; cladding; spacer mire;
thermohydraulic vibration; JOYO reactor; EBR-II reactor; wear/contact marking
mechanism; wear/contact marking range; thermodynamic properties; design;
feasibility studies
摘要：The surfaces of fuel pin cladding and spacer wire wound round it in the JOYO Mark-I and EBR-II test fuel were found to carry wear marks. Out-of-pile experiments indicated that simple hydraulic vibration could not constitute the cause of marking. Assuming the alternative factor of thermohydraulic vibration to be the cause, a model has been devised, applying which a method is proposed for estimating the ranges in which wear and contact marks can respectively be expected to occur. The two ranges are determined in terms of two parameters combining variables commonly used in practical fuel assembly design, and which are adopted as coordinates for a diagram in which data from actual fuel design are plotted. Data from actual reactor designs plotted in this diagram have proved to
fall into two distinct domains respectively covering
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