Advanced search
Publication Cover
Nuclear Technology Volume 180, 2012 - Issue 3: Special Issue on the Initial Release of MCNP6
Submit an article Journal homepage
430
Views
24
CrossRef citations to date
0
Altmetric
Technical Paper

Lightbridge Corporation’s Advanced Metallic Fuel for Light Water Reactors

James MaloneLightbridge Corporation, 1600 Tysons Boulevard, Suite 550 Mclean, Virginia 22102
,
Aaron TotemeierLightbridge Corporation, 1600 Tysons Boulevard, Suite 550 Mclean, Virginia 22102
,
Norton ShapiroLightbridge Corporation, 1600 Tysons Boulevard, Suite 550 Mclean, Virginia 22102
&
Swaminathan VaidyanathanLightbridge Corporation, 1600 Tysons Boulevard, Suite 550 Mclean, Virginia 22102
Pages 437-442 | Published online: 10 Aug 2017

References

  • W. F. Lyonet al., “Capabilities of the FALCON Steady State and Transient Fuel Performance Code,” Proc. 2004 Int. Mtg. LWR Fuel Performance, Orlando, Florida, September 19–22, 2004, American Nuclear Society (2004) (CD-ROM).
  • C. T. Walker and R. Manzel, “Fission Gas Release and Fuel Swelling at Burn-Ups Higher than 50 MWd/kgU,” Fission Gas Behavior in Water Reactor Fuels: Seminar Proceedings, Cadarache, France, September 26–29, 2000, p. 93, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2002).
  • J. H. Kittelet al., “History of Fast Reactor Fuel Development,” J. Nucl. Mater., 204, 1 (1993).
  • G. L. Hofman, R. G. Pahl, C. E. Lahm, and E. L. Porter, “Swelling Behavior of U-Pu-Zr Fuel,” Metallurgical Trans. A, 21A, 517 (1990).
  • F A. Rough, A. E. Austin, A. A. Bauer, and J. R. Doig, “The Stability and Existence Range of the Zirconium-Uranium Epsilon Phase,” BMI-1092, Battelle Memorial Institute (1956).
  • A. A. Bauer, “An Evaluation of the Properties and Behavior of Zirconium-Uranium Alloys,” BMI-1350, Battelle Memorial Institute (1959).
  • A. Glaser, “About the Enrichment Limit for Research Reactor Conversion: Why 20%?” presented at 27th Int. Mtg. Reduced Enrichment for Research and Test Reactors (RERTR), Boston, Massachusetts, November 6–10, 2005.
  • “Scientific Issues in Fuel Behavior,” Organisation for Economic Co-operation and Development Documents, p. 22, Nuclear Energy Agency Nuclear Science Committee Task Force (1995).
  • T. Warneret al., “Diffusion of Xe in Ta, Zr, and Pt,” Nucl. Instrum. Methods Phys. Res. A, 538, 135 (2005).
  • B. Leeet al., “Measurement of the Specific Heat of Zr-40 wt%U Metallic Fuel,” J. Nucl. Mater., 360, 315 (2007).
  • T. Ogawaet al., “Irradiation Behavior of Microspheres of U-Zr Alloys,” J. Alloys Compounds, 271–273, 670 (1993).
  • S. Isserow, “Corrosion Behavior of Defected Fuel Elements with U-2wt%Zr Core Clad with Zircaloy-2,” NMI-4364, Nuclear Metals, Inc. (July 1958).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Supercharge Your Next Research Paper: Research and write your next paper with Jenni AI.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.