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Fuel bundle to pressure tube fretting in Bruce and Darlington

Abstract

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  More>>
Authors:
Norsworthy, A G; Ditschun, A [1] 
  1. Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
Publication Date:
Dec 31, 1995
Product Type:
Conference
Report Number:
INIS-CA-0053; CONF-950623-
Reference Number:
SCA: 210400; PA: AIX-28:076178; EDB-97:143787; SN: 97001880584
Resource Relation:
Conference: 35. annual conference of the Canadian Nuclear Association and 16th annual conference of the Canadian Nuclear Society, Saskatoon (Canada), 4-7 Jun 1995; Other Information: PBD: 1995; Related Information: Is Part Of CNS proceedings of the 16. annual conference, volume I and II; Wight, A.L.; Loewer, R. [eds.]; PB: [2 v. ] p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BRUCE-8 REACTOR; FRETTING CORROSION; PRESSURE TUBES; BRUCE-1 REACTOR; CREEP; DARLINGTON-1 REACTOR; FUEL ELEMENT CLUSTERS; MECHANICAL VIBRATIONS; MODIFICATIONS; REACTOR MAINTENANCE; SPACERS; WEAR
OSTI ID:
546002
Research Organizations:
Canadian Nuclear Society, Toronto, ON (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE98603788; TRN: CA9700797076178
Availability:
INIS; OSTI as DE98603788
Submitting Site:
INIS
Size:
pp. [16]
Announcement Date:
Dec 10, 1997

Citation Formats

Norsworthy, A G, and Ditschun, A. Fuel bundle to pressure tube fretting in Bruce and Darlington. Canada: N. p., 1995. Web.
Norsworthy, A G, & Ditschun, A. Fuel bundle to pressure tube fretting in Bruce and Darlington. Canada.
Norsworthy, A G, and Ditschun, A. 1995. "Fuel bundle to pressure tube fretting in Bruce and Darlington." Canada.
@misc{etde_546002,
title = {Fuel bundle to pressure tube fretting in Bruce and Darlington}
author = {Norsworthy, A G, and Ditschun, A}
abstractNote = {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.}
place = {Canada}
year = {1995}
month = {Dec}
}