Influence of graphite discs, chamfers, and plenums on temperature distributions in high burnup fuel
- 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
- 2. Nuclear Power Plants Authority, Cairo (Egypt)
Description
Previous studies have demonstrated the desirability to increase the fuel burnups in CANDU reactors from 7-9 GW.d/t to 21 GW.d/t. At high burnups, one consideration in fuel integrity is fission gas pressure, which is predicted to reach about 13 MPa. The gas pressure can be kept below the coolant pressure (about 10 MPa) via a variety of options such as bigger chamfers, deeper dishes, central hole, and plenums. However, it is important to address the temperature perturbations produced by the bigger chamfers and plenums which in turn, affect the gas pressure. Another consideration in fuel integrity is to reduce the likelihood of fuel failures via environmentally assisted cracking. Insertion of graphite discs between neighbouring pellets will lower the pellet temperatures, hence, lower fission gas release and lower expansion of the pellet. Therefore, it is desired to quantify the effect of graphite discs on pellet temperatures. Thermal analyses of different fuel element geometries: with and without chamfers, graphite discs, and plenums were performed. The results indicate that the two-dimensional distributions of temperatures due to the presence of chamfers, graphite discs, or plenums can have a significant impact on the integrity of high burnup fuel as we have been able to quantify in this paper
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Additional details
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- AECL--9944
Conference
- Title
- 3. international conference on simulation methods in nuclear engineering.
- Dates
- 18-20 Apr 1990.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 25026013
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; E CODES; F CODES; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; FUEL INTEGRITY; SLIGHTLY ENRICHED URANIUM; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 1000-4000 K
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; URANIUM