Bent tube gauge design for ACR-1000 fuel bundles
Creators
- 1. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)
Description
The Bent Tube Gauge (BTG) is used in fuel bundle manufacturing to ensure that the bundles will pass through the fuel channel. Since the fuel bundle and the fuel channel dimensions, and in particular pressure tube dimensions change with time because of thermal, irradiation and gravity effects, the design of the BTG must account for irradiated bundle dimensions and the end-of-life pressure tube conditions. The BTG was first designed for the 28-element bundle in the Pickering A Nuclear Generating Station. All subsequent fuel bundle designs for CANDU reactors have used this BTG design. The methodology used for designing the Picketing BTG is examined and modifications to this methodology for application to the ACR-1000 are identified. Differences in CANFLEX-ACR fuel bundle and ACR-1000 fuel channel dimensions indicate the necessity for establishing a new BTG applicable to the ACR-1000. The assessment of the Pickering BTG design methodology and the changes to this approach that were used to design the ACR-1000 BTG are presented in this paper, as is the final configuration of the BTG selected for ACR-1000. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-93-3
- Imprint Title
- CANDU fuel : leading the renaissance. 10th international conference on CANDU fuel
- Imprint Pagination
- 133 Megabytes
- Journal Page Range
- [7 p.]
Conference
- Title
- 10. International conference on CANDU fuel
- Dates
- 5-8 Oct 2008
- Place
- Ottawa, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 41046723
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; FUEL FABRICATION PLANTS; PICKERING SITE; PRESSURE TUBES; SPENT FUEL ELEMENTS
- Descriptors DEC
- FUEL ASSEMBLIES; FUEL ELEMENTS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR SITES; REACTORS; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 1 fig.