Fuel management flexibility with single-ended refuelling in CANDU 3
Creators
- 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
Description
To meet the CANDU 3 design targets for low occupational exposures and for load following operation, the reference 37-element fuel bundle must perform as well as or better in a CANDU 3 than in previous CANDU's. With single-ended refuelling, the entire fuel column must be temporarily removed from the channel and placed inside the fuelling machine located at the downstream end of the fuel channel. The power boosts on upstream bundles as they slide through the centre of the core are acceptable for low burnup fuel, but not for bundles at normal discharge burnup. To eliminate the concerns about fuel performance, symmetric refuelling schemes are now planned for the central region of the core. This flattens the power profile in the axial direction and reduces peak bundle powers from 920 kW to levels below about 800 kW. These low powers will ensure good performance. The new refuelling schemes will result in some burnup loss (7.5%) but will ensure that the design targets are met. They will also have favourable impacts on safety and licensing primarily because of lower fuel element and bundle powers. (Author) 7 refs., 7 figs., tab
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 11th Annual Conference of the Canadian Nuclear Society
- Imprint Pagination
- 440 p.
- Journal Page Range
- p. 3.7-3.13.
- Report number
- INIS-mf--13847
Conference
- Title
- Canadian Nuclear Society 11. annual conference.
- Dates
- 3-6 Jun 1990.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 25031752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; FUEL MANAGEMENT; POWER COEFFICIENT; REACTOR FUELING; REACTOR SAFETY
- Descriptors DEC
- FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; PRESSURE TUBE REACTORS; REACTIVITY COEFFICIENTS; REACTORS; SAFETY; THERMAL REACTORS