Published 2000 | Version v1
Miscellaneous

Calculations supporting the shipment of irradiated CANFLEX demonstration fuel bundles

  • 1. Brunswick Nuclear Inc., Fredericton, New Brunswick (Canada)
  • 2. Point Lepreau Generating Station, Point Lepreau, New Brunswick (Canada)

Description

At the Point Lepreau Generating Station (PLGS), CANFLEX bundles were irradiated in the reactor core as part of the demonstration irradiation for the CANFLEX prototype fuel bundle. Some of these bundles were selected for shipment to the Chalk River Laboratories (CRL) in Ontario for post-irradiation examination. The Atomic Energy Control Board (AECB) and Atomic Energy of Canada Limited (AECL) require estimated values of several fuel parameters to satisfy the shipping regulations. The frequency of such calculations has increased over the last few years as NB Power continues its involvement with and support of CANDU fuel research and development. An analysis tool has been developed to determine the 'best-estimates' for the required fuel parameters. This paper briefly describes the irradiation of CANFLEX fuel, the shipping requirements, the analysis tool, the methods used to determine the estimates of the various spent fuel parameters and a summary of the supporting calculations for two CANFLEX bundles. (author)

Part of:
A better nuclear tomorrow: 21. annual CNS conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-66-6
Imprint Title
A better nuclear tomorrow
Imprint Pagination
49.1 Megabytes
Journal Page Range
[13 p.]

Conference

Title
21. annual CNS conference
Dates
11-14 Jun 2000
Place
Toronto, Ontario (Canada)

Optional Information

Notes
12 refs., 5 tabs., 1 fig.