Conceptual design of spent NuScale-derived DUPIC fuel in CANDU reactors to reduce spent fuel inventory
- 1. Univ. of Ontario Institute of Technology, Oshawa, ON (Canada)
- 2. CANDU Owners Group, Toronto, ON (Canada)
Description
A conceptual design of a NuScale Small Modular Reactor derived DUPIC (Direct Use of spent PWR fuel In CANDU reactors)fuel bundle design is proposed in this work with the overall objective of reducing the spent fuel footprint in Canada. The DUPIC nuclear fuel cycle, which was developed by Atomic Energy of Canada Limited and Korean Atomic Energy Research Institute, has been researched in China and Korea for many years in irradiating PWR derived spent fuel in CANDU reactors. Preliminary thermal analyses of the conceptual fuel bundle design, which has a similar geometry as a Bruce 37-element bundle, has demonstrated that it experiences similar fuel temperatures compared to a standard Bruce 37-element CANDU bundle under the same neutron flux. This work, which contributed to an undergraduate capstone project, generally looks towards the potential applications of CANDU reactors in reducing the NuScale SMR's spent fuel inventory. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-28-5
- Imprint Title
- Nuclear energy's value: aligned with community expectations. 39th Annual CNS conference and 43rd CNS/CNA student conference
- Imprint Pagination
- 175 Megabytes
- Journal Page Range
- [6 p.]
Conference
- Title
- 39. Annual CNS conference and 43. CNS/CNA student conference
- Dates
- 23-26 Jun 2019
- Place
- Ottawa, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 52027516
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs., 2 tabs., 2 figs.