Published September 2013 | Version v1
Journal article

Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel

  • 1. Materials Science and Technology Division, Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 (United States)
  • 2. Reactor and Nuclear Systems Division, Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 (United States)
  • 3. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555 (United States)

Description

A bending fatigue system developed to evaluate the response of spent nuclear fuel rods to vibration loads is presented. A U-frame testing setup is used for imposing bending loads on the fuel rod specimen. The U-frame setup consists of two rigid arms, side connecting plates to the rigid arms, and linkages to a universal testing machine. The test specimen's curvature is obtained through a three-point deflection measurement method. The tests using surrogate specimens with stainless steel cladding revealed increased flexural rigidity under unidirectional cyclic bending, significant effect of cladding-pellets bonding on the response of surrogate rods, and substantial cyclic softening in reverse bending mode. These phenomena may cast light on the expected response of a spent nuclear fuel rod. The developed U-frame system is thus verified and demonstrated to be ready for further pursuit in hot-cell tests

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2013.05.009

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2013.05.009;
PII
S0022-3115(13)00716-2;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
440
Journal Issue
1-3
Journal Page Range
p. 201-213
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.