Development of an internally cooled annular fuel bundle for pressurized heavy water reactors
Creators
- 1. Atomic Energy of Canada, Ltd., Chalk River Laboratories, Chalk River, ON (Canada)
Description
A number of preliminary studies have been conducted at Atomic Energy of Canada Limited to explore the potential of using internally cooled annular fuel (ICAF) in CANDU reactors including finite element thermo-mechanical modelling, reactor physics, thermal hydraulics, fabrication and mechanical design. The most compelling argument for this design compared to the conventional solid-rod design is the significant reduction in maximum fuel temperature for equivalent LERs (linear element ratings). This feature presents the potential for power up-rating or higher burnup and a decreased defect probability due to in-core power increases. The thermal-mechanical evaluation confirmed the significant reduction in maximum fuel temperatures for ICAF fuel compared to solid-rod fuel for equivalent LER. The maximum fuel temperature increase as a function of LER increase is also significantly less for ICAF fuel. As a result, the sheath stress induced by an equivalent power increase is approximately six times less for ICAF fuel than solid-rod fuel. This suggests that the power-increase thresholds to failure (due to stress-corrosion cracking) for ICAF fuel should be well above those for solid-rod fuel, providing improvement in operation flexibility and safety
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- Imprint Title
- Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads
- Imprint Pagination
- 1633 p.
- Journal Page Range
- p. 1087-1096
Conference
- Title
- International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads
- Acronym
- GLOBAL 2013
- Dates
- 29 Sep - 3 Oct 2013
- Place
- Salt Lake City, UT (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45085388
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; CRACKING; DESIGN; FINITE ELEMENT METHOD; FLEXIBILITY; FUEL ELEMENT CLUSTERS; FUEL RODS; NUCLEAR ENERGY; NUCLEAR FUELS; PHWR TYPE REACTORS; REACTOR PHYSICS; STRESS CORROSION; THERMAL HYDRAULICS
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ENERGY; ENERGY SOURCES; EVALUATION; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; THERMOCHEMICAL PROCESSES
Optional Information
- Notes
- 18 refs.