The study on grid-to-rod fretting wear models for PWR fuel
Creators
- 1. Dongguk University, College of Energy and Environment, 707 Seokjang-Dong, Gyeongju, Gyeongbuk 780-714 (Korea, Republic of)
Description
The fretting wear is found to be generated at grid-to-rod contact areas by flow-induced vibration. This flow-induced grid-to-rod fretting wear may be initiated at a certain critical grid-to-rod gap that strongly depends on the extent of flow-induced vibration and grid spring designs. Three fretting wear excitation mechanisms acting on the grid-to-rod fretting wear are summarized. In order to examine the impact of grid spring designs on the fretting wear rate, the fretting wear tests for three kinds of grid spring designs were carried out for 500 h, simulating the reactor flow conditions. In parallel, three grid-to-rod fretting wear models that include constant work rate model, constant work density rate model and linear work density rate model have been developed. The three fretting wear models were used to predict the fuel rod perforation times with the use of the fretting wear test results. It is said that the constant work density rate model or the linear work density rate model is quite effective in predicting the grid-to-rod fretting-induced rod failure time observed in commercial nuclear power plants.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2009.08.018Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2009.08.018;
- PII
- S0029-5493(09)00422-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 239
- Journal Issue
- 12
- Journal Page Range
- p. 2820-2824
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41079645
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- FRETTING CORROSION; FUEL ASSEMBLIES; FUEL ELEMENT FAILURE; FUEL RODS; MECHANICAL VIBRATIONS; PWR TYPE REACTORS; REACTOR LATTICE PARAMETERS; SPRINGS; WEAR
- Descriptors DEC
- CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; MACHINE PARTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.