Cermet nuclear fuels have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle provide intriguing options for using thoria based cermet nuclear fuel in advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. The following paper will first describe the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model will then be applied to the design and analysis of thorium/uranium/zirconium metal matrix fuel pins for light water reactors using neutronic simulation methods.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3598-7
PROCEEDINGS PAPER
Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis
Thomas J. Downar,
Thomas J. Downar
Purdue University, West Lafayette, IN
Search for other works by this author on:
Sean M. McDeavitt,
Sean M. McDeavitt
Argonne National Laboratory, Argonne, IL
Search for other works by this author on:
S. T. Revankar,
S. T. Revankar
Purdue University, West Lafayette, IN
Search for other works by this author on:
A. A. Solomon,
A. A. Solomon
Purdue University, West Lafayette, IN
Search for other works by this author on:
T. K. Kim
T. K. Kim
Argonne National Laboratory, Argonne, IL
Search for other works by this author on:
Thomas J. Downar
Purdue University, West Lafayette, IN
Sean M. McDeavitt
Argonne National Laboratory, Argonne, IL
S. T. Revankar
Purdue University, West Lafayette, IN
A. A. Solomon
Purdue University, West Lafayette, IN
T. K. Kim
Argonne National Laboratory, Argonne, IL
Paper No:
ICONE10-22305, pp. 47-57; 11 pages
Published Online:
March 4, 2009
Citation
Downar, TJ, McDeavitt, SM, Revankar, ST, Solomon, AA, & Kim, TK. "Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 4. Arlington, Virginia, USA. April 14–18, 2002. pp. 47-57. ASME. https://doi.org/10.1115/ICONE10-22305
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
A Computational Model of the Mark-IV Electrorefiner: Phase I—Fuel Basket/Salt Interface
J. Eng. Gas Turbines Power (September,2009)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
A Once-Through Fuel Cycle for Fast Reactors
J. Eng. Gas Turbines Power (October,2010)
Related Chapters
Current Perspectives on Zirconium Use in Light Water Reactor Fuel and Its Continued Use in Nuclear Power
Zirconium in the Nuclear Industry: 20th International Symposium
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code
Nuclear Fuel Cycle
Non-Proliferation Nuclear Forensics: Canadian Perspective