Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel
Creators
- 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.2013.05.009Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45070108
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Descriptors DEI
- BENDING; CLADDING; FATIGUE; FUEL RODS; MATERIALS TESTING; SPENT FUELS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DEFORMATION; DEPOSITION; ENERGY SOURCES; FUEL ELEMENTS; FUELS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; STEELS; SURFACE COATING; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.