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Title: Non-Destructive Characterization of UO2+x Nuclear Fuels

Journal Article · · Microscopy Today
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  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Carnegie Mellon Univ., Pittsburgh, PA (United States)
  3. Argonne National Lab. (ANL), Argonne, IL (United States)
+ Show Author Affiliations

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE; USDOE Office of Science - Office of Basic Energy Sciences - Scientific User Facilities Division; Los Alamos National Laboratory (LANL) - Laboratory Directed Research and Development (LDRL)
Grant/Contract Number:
AC52-06NA25396; AC02-06CH11357
OSTI ID:
1412908
Alternate ID(s):
OSTI ID: 1439862
Report Number(s):
LA-UR-17-28316; applab; TRN: US1800409
Journal Information:
Microscopy Today, Vol. 25, Issue 06; ISSN 1551-9295
Publisher:
Cambridge University PressCopyright Statement
Country of Publication:
United States
Language:
English

References (17)

Grain Boundaries in Uranium Dioxide: Scanning Electron Microscopy Experiments and Atomistic Simulations: Grain Boundaries in Uranium Dioxide journal January 2011
Three-Dimensional Characterization of Sintered UO 2+ x : Effects of Oxygen Content on Microstructure and Its Evolution journal May 2013
First-principles DFT modeling of nuclear fuel materials journal April 2012
The effect of grain size on the swelling and gas release properties of uo2 during irradiation journal February 1974
Forward modeling method for microstructure reconstruction using x-ray diffraction microscopy: Single-crystal verification journal December 2006
Observation of recovery and recrystallization in high-purity aluminum measured with forward modeling analysis of high-energy diffraction microscopy journal June 2012
In-situ observation of bulk 3D grain evolution during plastic deformation in polycrystalline Cu journal April 2015
Three-Dimensional X-Ray Diffraction Microscopy book January 2004
Implementation and verification of a microstructure-based capability for modeling microcrack nucleation in LSHR at room temperature journal March 2015
New model of equiaxed grain growth in irradiated UO2 journal February 1999
Demonstration of near Field High Energy X-Ray Diffraction Microscopy on High-Z Ceramic Nuclear Fuel Material journal February 2014
New opportunities for quantitative tracking of polycrystal responses in three dimensions journal August 2015
Swelling in UO 2 under conditions of gas release journal July 1974
The sintering mechanism in journal January 1977
Theory of Grain Growth in Porous Compacts journal December 1966
Influence of Stoichiometry on the Rate of Grain Growth of UO2 journal August 1963
The distribution of rotation axes in a random aggregate of cubic crystals journal February 1964

Cited By (1)

Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons journal November 2019

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
HEDM
UO2
grain size
microstructure
nuclear fuels