A Power-Rate-Dependent Model for Pellet/Cladding Mechanical Interaction

Author:

Chao Chlng-Kong1,Tseng Che-Chung2

Affiliation:

1. National Taiwan Institute of Technology Department of Mechanical Engineering, 43, Keelung Road, Section 4 Taipei, Taiwan

2. Institute of Nuclear Energy Research Nuclear Fuel and Material Division, P.O. Box 3-14, Lungtan, Taiwan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference20 articles.

1. Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review

2. T. NAKAJIMA, M. ICHIKAWA, Y. IWANO, K. ITO, H. SAITO, K. KASHIMA, M. KINOSHITA, and T. OKUBO, “FEMAXI-III, A Computer Code for the Analysis of Thermal and Mechanical Behavior of Fuel Rods,” JAERI-1298, Japan Atomic Energy Research Institute (Dec. 1985).

3. Mechanics and physics of energy density theory

4. Size effect of cylindrical specimens with fatigue cracks

Cited by 4 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Effect of hydride embrittlement on creep life of spent fuel cladding;Journal of the Chinese Institute of Engineers;2011-01

2. Creep crack growth on spent fuel zircaloy cladding in interim storage;Theoretical and Applied Fracture Mechanics;2007-02

3. Fuel rod load follow analysis;Journal of Nuclear Materials;1996-04

4. Study on optimum zirconium liner thickness for barrier fuel;Nuclear Engineering and Design;1993-11

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