Published 2010 | Version v1
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Post-irradiation examination of CANDU fuel bundles fuelled with (Th, Pu)O2

Description

AECL has extensive experience with thoria-based fuel irradiations as part of an ongoing R&D program on thorium within the Advanced Fuel Cycles Program. The BDL-422 experiment was one component of the thorium program that involved the fabrication and irradiation testing of six Bruce-type bundles fuelled with (Th, Pu)O2 pellets. The fuel was manufactured in the Recycle Fuel Fabrication Laboratories (RFFL) at Chalk River allowing AECL to gain valuable experience in fabrication and handling of thoria fuel. The fuel pellets contained 86.05 wt.% Th and 1.53 wt.% Pu in (Th, Pu)O2. The objectives of the BDL-422 experiment were to demonstrate the ability of 37-element geometry (Th, Pu)O2 fuel bundles to operate to high burnups up to 1000 MWh/kgHE (42 MWd/kgHE), and to examine the (Th, Pu)O2 fuel performance. This paper describes the post-irradiation examination (PIE) results of BDL-422 fuel bundles irradiated to burnups up to 856 MWh/kgHE (36 MWd/kgHE), with power ratings ranging from 52 to 67 kW/m. PIE results for the high burnup bundles (>1000 MWh/kgHE) are being analyzed and will be reported at a later date. The (Th, Pu)O2 fuel performance characteristics were superior to UO2 fuel irradiated under similar conditions. Minimal grain growth was observed and was accompanied by benign fission gas release and sheath strain. Other fuel performance parameters, such as sheath oxidation and hydrogen distribution, are also discussed. (author)

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Additional details

Publishing Information

Imprint Pagination
15 p.
Report number
AECL-CW--124950-CONF-003

Conference

Title
11. International Conference on CANDU Fuel
Dates
17-20 Oct 2010
Place
Niagara Falls, ON (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49101473
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Quality check status
Yes
Descriptors DEI
BURNUP; CANDU TYPE REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; THORIUM;
Descriptors DEC
ACTINIDES; ELEMENTS; ENERGY SOURCES; FUEL ASSEMBLIES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS;

Optional Information

Notes
9 refs., 3 tabs., 11 figs. This record replaces 49041757