Published July 1976
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Calculation of axial flux distribution in CANDU fuel bundles
Description
A knowledge of axial flux distributions in various CANDU fuel bundle designs is necessary for their proper evaluation. In particular, the peaking of the flux near the ends of the elements is an important factor in the determination of a reactor's critical power ratio. In the present report the discrete-ordinates method is compared with experiment for a fuel bundle which admits a 2-D representation, and a method is presented for dealing with designs requiring a 3-D calculation. The latter method is compared with experiment for a bundle with staggered plenums. (author)
Availability note (English)
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8299532.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- AECL--5390
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 8299532
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CANDU TYPE REACTORS; FLUX DENSITY; FUEL ELEMENT CLUSTERS; NEUTRON FLUX; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 8 refs.