Published April 1996 | Version v1
Miscellaneous

CANFLEX : A new CANDU fuel bundle with expanded operating capabilities

  • 1. Atomic Energy of Canada Limited, Ottawa (Canada)
  • 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

CANFLEX1 is a 43-element CANDUR bundle, which is being developed jointly by AECL and KAERI, to facilitate the use of various advanced fuel cycles in CANDU reactors through the provision of enhanced operating margins in the bundle design. This 43-element bundle design uses two diameters of elements (13.5 and 11.5 mm) to reduce element ratings by 20%, yet maintain the same bundle power, and a uranium content very close to that of a standard 37-element bundle. The CANFLEX design also includes the use of critical-heat-flux (CHF) enhancing appendages, to increase the minimum CHF ratio, or dryout margin of the bundle. The combination of these two features also makes the CANFLEX bundle of interest for use in older CANDU reactors, where it can compensate for any operating margin lost because of steam-generator fouling or pressure tube creep. The program to develop and demonstrate the CANFLEX bundle is currently at the stage of separate, bundle demonstration tests, including demonstration irradiation in the NRU reactor, flow testing in the KAERI hydraulics laboratory, reactor physics characterization tests in the ZED-2 reactor, fuelling machine compatibility tests at the Sheridan Park Engineering Laboratory, and CHF tests in a thermal hydraulics Laboratory at Chalk River. A dialogue is underway with utilities, focussed on the demonstration irradiation in power reactors, and to support this, a Fuel Design Manual and other safety analysis reports are being prepared

Part of:
Proceedings of the 11th KAIF/KNS Annual Conference

Additional details

Publishing Information

Publisher
KAIF-KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the 11th KAIF/KNS Annual Conference
Imprint Pagination
864 p.
Journal Page Range
p. 721-730

Conference

Title
11. KAIF/KNS Annual Conference
Dates
11-12 Apr 1996
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44076803
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; CREEP; CRITICAL HEAT FLUX; DESIGN; FUEL ELEMENT CLUSTERS; IRRADIATION; KAERI; REACTOR OPERATION
Descriptors DEC
CANADIAN ORGANIZATIONS; FUEL ASSEMBLIES; HEAT FLUX; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information

Notes
Imprint:4 refs, 4 figs, 1 tab