Clean Core's ANEELTM fuel for PHWRs: a significant increase in burnup and decrease in spent fuel volume
- 1. Massachusetts Institute of Technology, Cambridge, MA (United States)
- 2. Clean Core Inc., Oak Brook, IL (United States)
- 3. Royal Military College of Canada, Kingston, ON (Canada)
Description
As demand for carbon-free energy increases, the role of nuclear energy in Canada and abroad will have to expand. The efficient utilization of nuclear fuel in terms of energy extraction per mass (burnup) and volume of generated spent fuel must be further optimized as CANDU refurbishments are completed and new reactors are projected to come online. Thoria-enriched urania has potential in increasing the current discharge burnup realized by natural uranium fuel. Fundamentally, this is done through: i. Leveraging the improved thermo physical properties of Thoria (conductivity and melting point) that results in less fuel cracking. ii. Thoria greater retention of fission gases at high burnup per given temperature that limits fuel internal rod pressure. Clean Core Inc., a Chicago based company, is in the process of testing and demonstrating the use of an evolutionary thorium-based fuel for the Pressurized Heavy Water Reactors (PHWRs). Our HALEU (high-assay low-enriched uranium) and Thorium fuel technology, named Advanced Nuclear Energy for Enriched Life (ANEELTM), reduces life-cycle operating costs in PHWR while increasing safety margins. This paper describes the benefits of an open thoria-urania fuel cycle from the point of view of uranium utilization, safety margin and spent fuel volume. Long-term storage of irradiated ANEELTM fuel with respect to repository disposal requirements will also be discussed. (author)
Availability note (English)
Available as a slide presentation also.Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- Imprint Title
- The new nuclear: pathways to securing a clear energy future. 43rd Annual CNS conference and 48th CNS/CNA student conference
- Imprint Pagination
- vp.
- Journal Page Range
- [10 p.]
Conference
- Title
- 43. Annual Canadian Nuclear Society conference; 48. CNS/CNA student conference
- Dates
- 16-19 Jun 2024
- Place
- Saskatoon, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 56007520
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, Numerical Data
- Descriptors DEI
- AFTER-HEAT; BURNUP; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CRACKING; EFFICIENCY; ENRICHED URANIUM; NUCLEAR FUELS; NUMERICAL DATA; OPEN FUEL CYCLE; PHWR TYPE REACTORS; PHYSICAL PROPERTIES; RADIOACTIVE WASTE STORAGE; SAFETY MARGINS; SPENT FUELS; THERMODYNAMIC PROPERTIES; THORIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; CHEMICAL REACTIONS; DATA; DECOMPOSITION; ELEMENTS; ENERGY SOURCES; FUEL CYCLE; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; PYROLYSIS; RADIOACTIVE WASTE MANAGEMENT; REACTOR MATERIALS; REACTORS; SIMULATION; STORAGE; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; THORIUM COMPOUNDS; URANIUM; WASTE MANAGEMENT; WASTE STORAGE
Optional Information
- Notes
- 8 refs., 2 tabs., 5 figs.