Fuel bundle to pressure tube fretting in Bruce and Darlington
Description
As the fuel channel elongates due to creep, the fuel string moves relative to the inlet until the fuel pads at the inboard end eventually separate from the spacer sleeve, and the fuel resides on the burnish mark of the pressure tube. The bundle is then supported in a fashion which contributes to increased levels of vibration. Those pads which (due to geometric variation) have contact loads with the pressure tube within a certain range, vibrate, and cause significant fretting on the burnish mark, and further along at the midplane of the bundle. Inspection of the pressure tubes in Bruce A, Bruce B, and Darlington has revealed fret damage up to 0.55 mm at the burnish mark and slightly lower than this at the inlet bundle midplane. To date, all fret marks have been dealt with successfully without the need for tube replacement, but a program of work has been initiated to understand the mechanism and reduce the fretting. Such understanding is necessary to guide future design changes to the fuel bundle, to guide future inspection programs, to guide maintenance programs, and for longer term strategic planning. This paper discusses how the understanding of fretting has evolved and outlines a current hypothesis for the mechanism of fretting. The role of bundle geometry, excitation forces, and reactor conditions are reviewed, along with options under consideration to mitigate damage. (author). 4 refs., 2 tabs., 13 figs
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28076178.pdf
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Additional details
Publishing Information
- Imprint Title
- CNS proceedings of the 16. annual conference, volume I and II
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [16 p.].
- Report number
- INIS-CA--0053
Conference
- Title
- 16. Annual conference of the Canadian Nuclear Society.
- Dates
- 4-7 Jun 1995.
- Place
- Saskatoon, SK (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28076178
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRUCE-1 REACTOR; BRUCE-8 REACTOR; CREEP; DARLINGTON-1 REACTOR; FRETTING CORROSION; FUEL ELEMENT CLUSTERS; MECHANICAL VIBRATIONS; MODIFICATIONS; PRESSURE TUBES; REACTOR MAINTENANCE; SPACERS; WEAR
- Descriptors DEC
- CANDU TYPE REACTORS; CHEMICAL REACTIONS; CORROSION; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MAINTENANCE; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TUBES