Published November 1999 | Version v1
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Demonstration irradiation of CANFLEX in Pt. Lepreau

  • 1. Chalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, ON (Canada)
  • 2. New Brunswick Power, Pt. Lepreau, New Brunswick (Canada)
  • 3. Korea Atomic Energy Research Institute, Taejon City (Korea, Republic of)

Description

The demonstration irradiation of CANFLEX in the Point Lepreau Generating Station (PLGS) in New Brunswick, Canada, will mark a major milestone towards delivering this new fuel to CANDU utilities. One high-powered and one instrumented fuel channel are being fuelled with CANFLEX bundles to establish irradiation experience in a power reactor. As CANFLEX is discharged into the reactor bays, it win be examined by fuel experts from PLGS and AECL. Several irradiated CANFLEX bundles will be shipped to Chalk River for extensive post-irradiation examination. CANFLEX is the latest fuel carrier in the evolution of CANDU fuel. Its design has been driven to provide higher dryout powers and lower peak element ratings, while being fully compatible with existing CANDU stations and addressing the development requirements for future advanced CANDU stations. The design has been tuned through analysis and testing at AECL and KAERI. The final CANFLEX design has undergone extensive analysis, performance testing and critical industry review. Safety performance has been analyzed and documented in a licensing submission to the Canadian regulator, the Atomic Energy Control Board, for approval to proceed with the demonstration irradiation. Because CANFLEX is fully compatible with existing plants, CANDU 6 stations can simply substitute CANFLEX-NU for 37-element fuel and achieve improved reactor operating and safety margins, and higher critical channel powers. For CANDU designers, CANFLEX provides the opportunity to benefit from the use of slightly enriched uranium (SEU) or recycled uranium (RU) from reprocessed spent PWR fuel. Enrichment can be used in one of several ways: to increase the power from a given reactor core size through flattening the radial channel power profile; to increase the fuel burnup and reduce the quantity of spent fuel; to improve fuel cycle economics, both front- and back-end; and, in general, to provide greater flexibility in reactor design. (author)

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Part of:
Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting
Imprint Pagination
370 p.
Journal Page Range
p. 153-162
ISSN
1011-4289
Report number
IAEA-TECDOC--1122

Conference

Title
Technical committee meeting on fuel cycle options for light water reactors and heavy water reactors
Dates
28 Apr - 1 May 1998
Place
Victoria (Canada)

Optional Information

Notes
13 refs, 4 figs, 1 tab