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Journal of Nuclear Science and Technology Volume 36, 1999 - Issue 6
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Original Articles

The Occurrence of Wear Marks on Fast Reactor Fuel Pin Cladding

Akira OTSUBO Japan Nuclear Cycle Development Institute , Siraki, Tsuruga-shi, 919-1279
,
Toshio OKADA Japan Nuclear Cycle Development Institute , Siraki, Tsuruga-shi, 919-1279
,
Nobutomo TAKAHASHI Japan Nuclear Cycle Development Institute , Siraki, Tsuruga-shi, 919-1279
,
Kazujirou SATO Japan Nuclear Cycle Development Institute , Siraki, Tsuruga-shi, 919-1279
&
Naozou HATTORI Japan Nuclear Cycle Development Institute , Siraki, Tsuruga-shi, 919-1279
Pages 522-534 | Received 13 Jul 1998, Published online: 15 Feb 2012

Citations (7)

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Read on this site (1)

C. A. Nixon, W. R. Marcum, K. M. Steer, R. B. Jackson, M. G. Martin & A. W. Weiss. (2020) On the Fluid Structure Interactions of a Wire-Wrapped Pin Bundle. Nuclear Technology 206:2, pages 218-230.
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Articles from other publishers (6)

W.R. Marcum, C.A. Nixon, M. Martin, K.M. Steer, R.B. Jackson & A.W. Weiss. (2023) Flow induced vibration measurement of a full-length sodium fast reactor fuel bundle. Nuclear Engineering and Design 408, pages 112322.
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Xu-dong Chen, Shuo Feng, Li-wen Wang, Rui Tang, Fan Zhang, Shi-lin Ming & Zhen-bing Cai. (2022) Effect of QPQ on the fretting wear behavior of TP316H steel at varying temperatures in liquid sodium. Journal of Nuclear Materials 562, pages 153583.
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Henri Dolfen, Jeroen De Ridder, Landon Brockmeyer, Elia Merzari, Graham Kennedy, Katrien Van Tichelen & Joris Degroote. (2022) A multi-stage approach of simulating turbulence-induced vibrations in a wire-wrapped tube bundle for fretting wear prediction. Journal of Fluids and Structures 109, pages 103460.
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C. A. Nixon, W. R. Marcum, K. M. Steer & R. B. Jackson. (2018) A New Method for Experimentally Quantifying Dynamic Deflection of a Cylindrical Structure. Experimental Mechanics 58:9, pages 1351-1369.
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Jianqiang Shan, Henan Wang, Wei Liu, Linxing Song, Xuanxiang Chen & Yang Jiang. (2014) Subchannel Analysis of Wire Wrapped SCWR Assembly. Science and Technology of Nuclear Installations 2014, pages 1-8.
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P. Diller, N. Todreas & P. Hejzlar. (2009) Thermal-hydraulic analysis for wire-wrapped PWR cores. Nuclear Engineering and Design 239:8, pages 1461-1470.
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