Published 1995 | Version v1
Miscellaneous Open

Characteristics of CANDU fuel bundles that caused pressure tube fretting at the bundle midplane

Creators

  • 1. Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
  • 2. Ontario Hydro, Toronto, ON (Canada)

Description

Detailed measurements on new bundles, and those that caused fretting during in- and out-reactor tests, have given insight into the factors responsible for fretting at the midplane of the inlet bundle. Bottom fuel elements that were attached near radial endplate spokes and had inboard bearing pads in the rolled joint cavity produced a significant portion of the observed fret marks. These elements are influenced by several driving forces that deflect the centre bearing pads towards the pressure tube surface. The evidence suggests that slight changes in bundle design may be possible to reduce pressure tube fretting. (author). 4 refs., 3 tabs., 8 figs

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Part of:
CNS proceedings of the 16. annual conference, volume I and II

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) [19 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
28076186
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BRUCE-8 REACTOR; CREEP; DARLINGTON-3 REACTOR; DESIGN; FRETTING CORROSION; FUEL ELEMENT CLUSTERS; MECHANICAL TESTS; MECHANICAL VIBRATIONS; MODIFICATIONS; PRESSURE TUBES; PRIMARY COOLANT CIRCUITS; REACTOR MAINTENANCE; SPACERS; TOLERANCE; WEAR
Descriptors DEC
CANDU TYPE REACTORS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MAINTENANCE; MATERIALS TESTING; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; TUBES

Optional Information