Calculations supporting the shipment of irradiated CANFLEX demonstration fuel bundles
Creators
- 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)
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)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 35088094
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ATOMIC ENERGY OF CANADA LTD; CANADIAN AECB; CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; IRRADIATION; POINT LEPREAU-1 REACTOR; REACTOR CORES; SPENT FUELS
- Descriptors DEC
- CANADIAN ORGANIZATIONS; CANDU TYPE REACTORS; ENERGY SOURCES; FUEL ASSEMBLIES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 12 refs., 5 tabs., 1 fig.