Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors
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- 作者：Mark A. Christona ; b ; machriston@c-sciences.com" class="auth_mail" title="E-mail the corresponding author ; Roger Lud ; lur@westinghouse.com" class="auth_mail" title="E-mail the corresponding author ; Jozsef Bakosic ; jbakosi@lanl.gov" class="auth_mail" title="E-mail the corresponding author ; Balasubramanya T. Nadigac ; balu@lanl.gov" class="auth_mail" title="E-mail the corresponding author ; Zeses Karoutasd ; karoutze@westinghouse.com" class="auth_mail" title="E-mail the corresponding author ; Markus Berndtc ; berndt@lanl.gov" class="auth_mail" title="E-mail the corresponding author
- 关键词：Thermal-hydraulics ; Nuclear reactor ; Rod-bundles ; Grid-to-rod fretting ; Implicit large-eddy simulation ; Nonlinear structural dynamics ; Incompressible flow ; Monotonicity-preserving advection
- 刊名：Journal of Computational Physics
- 出版年：2016
- 出版时间：1 October 2016
- 年：2016
- 卷：322
- 期：Complete
- 页码：142-161
- 全文大小：4587 K
文摘
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A new approach for predicting grid-to-rod fretting wear in reactor fuel is presented.
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ILES validation is performed using data for a 5×5 fuel rod bundle.
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Richardson extrapolation of statistical fuel rod forces is used to bound wear work-rates.