The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Apr. 10, 2018

Filed:

Apr. 08, 2011
Applicants:

Charles E. Ahlfeld, LaJolla, CA (US);

William W. Bowen, Kennewick, WA (US);

Roderick A. Hyde, Redmond, WA (US);

Ronald L. Klueh, Knoxville, TN (US);

Sean M. Mcdeavitt, Bryan, TX (US);

Joshua C. Walter, Kirkland, WA (US);

Steven R. Kirkendall, Richland, WA (US);

Inventors:

Charles E. Ahlfeld, LaJolla, CA (US);

William W. Bowen, Kennewick, WA (US);

Roderick A. Hyde, Redmond, WA (US);

Ronald L. Klueh, Knoxville, TN (US);

Sean M. McDeavitt, Bryan, TX (US);

Joshua C. Walter, Kirkland, WA (US);

Steven R. Kirkendall, Richland, WA (US);

Assignee:

TerraPower, LLC, Bellevue, WA (US);

Attorney:
Primary Examiner:
Int. Cl.
CPC ...
G21C 3/17 (2006.01); G21C 3/16 (2006.01); G21C 3/58 (2006.01); G21C 3/62 (2006.01); G21C 21/04 (2006.01); G21C 3/04 (2006.01);
U.S. Cl.
CPC ...
G21C 3/16 (2013.01); G21C 3/044 (2013.01); G21C 3/17 (2013.01); G21C 3/58 (2013.01); G21C 3/623 (2013.01); G21C 21/04 (2013.01); Y02E 30/38 (2013.01);
Abstract

A nuclear fuel includes a volume of a nuclear fuel material defined by a surface, the nuclear fuel material including a plurality of grains, some of the plurality of grains having a characteristic length along at least one dimension that is smaller than or equal to a selected distance, wherein the selected distance is suitable for maintaining adequate diffusion of a fission product from a grain interior to a grain boundary in some of the grains, the nuclear fuel material including a boundary network configured to transport the fission product from at least one grain boundary of some of the grains to the surface of the volume of the nuclear fuel material.


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