Published 2001 | Version v1
Book Metadata-only

Mechanical fretting endurance test of CANFLEX fuel bundle

Creators

  • 1. Korea Atomic Energy Research Institute, Yusong-ku, Taejon City (Korea, Republic of)

Description

A 3000 hour mechanical fretting endurance test for the verification of the CANFLEX fuel bundle was performed in the KAERI CANDU Hot Test Loop facility. The test conditions were the same as the real reactor normal operating conditions. After the test, the dimensions and fretting wears of the test bundles and the pressure tube were carefully measured and inspected, which met the acceptance design criteria. Also, the historical trends of fretting wears of bearing pads and spacers were evaluated with the test results. (author)

Part of:
CANDU fuel for the future

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-70-4
Imprint Title
CANDU fuel for the future
Imprint Pagination
2 v.
Journal Page Range
(v.1) p. 51-61

Conference

Title
7. International CANDU fuel conference proceedings
Dates
23-27 Sep 2001
Place
Kingston, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
34078567
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; COOLANT LOOPS; FRETTING CORROSION; FUEL CYCLE; FUEL ELEMENT CLUSTERS; KAERI; MECHANICAL VIBRATIONS; NUCLEAR FUELS; PHWR TYPE REACTORS; REPUBLIC OF KOREA; TURBULENT FLOW; WEAR
Descriptors DEC
ASIA; CANADIAN ORGANIZATIONS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; DEVELOPING COUNTRIES; ENERGY SOURCES; ENERGY SYSTEMS; FLUID FLOW; FUEL ASSEMBLIES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; MATERIALS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS

Optional Information

Notes
2 refs., 1 tab., 15 figs.