Published August 1997
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Analysis of fatigue strength for CANFLEX endplate
Description
A stress analysis of the endplate was performed under the condition that the CANFLEX fuel bundle was subjected to the axial flow in the reactor. The model developed by Tayal and Choo for the application to the standard 37-element bundle for the same purpose was used in the analysis. The model developed by Paidoussis for predicting the vibration amplitude of an element was also used, but before the use the model was validated with the results obtained from excitation tests of CANFLEX fuel elements. (author). 6 refs., 10 figs
Availability note (English)
Available from INIS in electronic form and/or on microfiche .Files
29025585.pdf
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Additional details
Publishing Information
- Imprint Pagination
- [33 p.].
- Report number
- KAERI/TR--896/97
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 29025585
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; COOLANTS; FATIGUE; FUEL ELEMENTS; FUEL INTEGRITY; PERFORMANCE TESTING; STRESSES
- Descriptors DEC
- HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS