SuperCritical Water-cooled nuclear Reactor (SCWR) options are one of the six reactor options identified in Generation IV International Forum (GIF). In these reactors the light-water coolant is pressurized to supercritical pressures (up to approximately 25 MPa). This allows the coolant to remain as a single-phase fluid even under supercritical temperatures (up to approximately 625°C). SCW Nuclear Power Plants (NPPs) are of such great interest, because their operating conditions allow for a significant increase in thermal efficiency when compared to that of modern conventional water-cooled NPPs. Direct-cycle SCW NPPs do not require the use of steam generators, steam dryers, etc. allowing for a simplified NPP design. This paper shows that new nuclear fuels such as Uranium Carbide (UC) and Uranium Dicarbide (UC2) are viable option for the SCWRs. It is believed they have great potential due to their higher thermal conductivity and corresponding to that lower fuel centerline temperature compared to those of conventional nuclear fuels such as uranium dioxide, thoria and MOX. Two conditions that must be met are: 1) keep the fuel centreline temperature below 1850°C (industry accepted limit), and 2) keep the sheath temperature below 850°C (design limit). These conditions ensure that SCWRs will operate efficiently and safely. It has been determined that Inconel-600 is a viable option for a sheath material. A generic SCWR fuel channel was considered with a 43-element bundle. Therefore, bulk-fluid, sheath and fuel centreline and HTC profiles were calculated along the heated length of a fuel channel.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4354-3
PROCEEDINGS PAPER
Thermal Design Options Using Uranium Carbide and Uranium Dicarbide in SCWR Uniformly-Heated Fuel Channel Available to Purchase
Leyland J. Allison,
Leyland J. Allison
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Lisa Grande,
Lisa Grande
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Sally Mikhael,
Sally Mikhael
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Adrianexy Rodriguez Prado,
Adrianexy Rodriguez Prado
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Bryan Villamere,
Bryan Villamere
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Igor Pioro
Igor Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
Search for other works by this author on:
Leyland J. Allison
University of Ontario Institute of Technology, Oshawa, ON, Canada
Lisa Grande
University of Ontario Institute of Technology, Oshawa, ON, Canada
Sally Mikhael
University of Ontario Institute of Technology, Oshawa, ON, Canada
Adrianexy Rodriguez Prado
University of Ontario Institute of Technology, Oshawa, ON, Canada
Bryan Villamere
University of Ontario Institute of Technology, Oshawa, ON, Canada
Igor Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
Paper No:
ICONE17-75975, pp. 703-712; 10 pages
Published Online:
February 25, 2010
Citation
Allison, LJ, Grande, L, Mikhael, S, Rodriguez Prado, A, Villamere, B, & Pioro, I. "Thermal Design Options Using Uranium Carbide and Uranium Dicarbide in SCWR Uniformly-Heated Fuel Channel." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. Brussels, Belgium. July 12–16, 2009. pp. 703-712. ASME. https://doi.org/10.1115/ICONE17-75975
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Thermal Aspects of Uranium Carbide and Uranium Dicarbide Fuels in Supercritical Water-Cooled Nuclear Reactors
J. Eng. Gas Turbines Power (February,2011)
PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?
Mechanical Engineering (August,2011)
Thermal-Design Options for Pressure-Channel SCWRS With Cogeneration of Hydrogen
J. Eng. Gas Turbines Power (January,2009)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Combined Cycle Power Plant
Energy and Power Generation Handbook: Established and Emerging Technologies
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code