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Title: Accident-tolerant oxide fuel and cladding

Systems and methods for accident tolerant oxide fuel. One or more disks can be placed between fuel pellets comprising UO.sub.2, wherein such disks possess a higher thermal conductivity material than that of the UO.sub.2 to provide enhanced heat rejection thereof. Additionally, a cladding coating comprising zircaloy coated with a material that provides stability and high melting capability can be provided. The pellets can be configured as annular pellets having an annulus filled with the higher thermal conductivity material. The material coating the zircaloy can be, for example, Zr.sub.5Si.sub.4 or another silicide such as, for example, a Zr-Silicide that limits corrosion. The aforementioned higher thermal conductivity material can be, for example, Si, Zr.sub.xSi.sub.y, Zr, or Al.sub.2O.sub.3.
Inventors:
Issue Date:
OSTI Identifier:
1360772
Assignee:
U.S. Department of Energy HQPR
Patent Number(s):
9,666,310
Application Number:
13/847,009
Contract Number:
AC07-05-ID114517
Resource Relation:
Patent File Date: 2013 Mar 19
Research Org:
Washington Procurement Operations Office, Washington, DC (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Other works cited in this record:

Ductile irradiated zirconium alloy
patent, November 1989

Method for fabricating mixed oxide fuel
patent, August 1999

Zirconium-alloy clad fuel rods containing metal oxide for mitigation of secondary hydriding
patent, February 2004

Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel
patent, February 2010

Triuranium disilicide nuclear fuel composition for use in light water reactors
patent, October 2012

Cladding Tube For Nuclear Fuel Rod, Method And Apparatus For Manufacturing A Cladding Tube
patent-application, September 2011

Molybdenum Silicide Composite Material
patent-application, October 2011

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