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Title: High temperature nanoindentation of (U,Ce)O2 compounds

Journal Article · · Nuclear Engineering and Design

Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89233218CNA000001
OSTI ID:
2332908
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 423 Journal Issue: C; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (45)

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A procedure for extracting primary and secondary creep parameters from nanoindentation data journal October 2013
Plasticity of UO2 studied and quantified via elevated temperature micro compression testing journal November 2019
Mechanical properties of UO2 thin films under heavy ion irradiation using nanoindentation and finite element modeling journal October 2016
Hot hardness and indentation creep studies on Zr1Nb1Sn0.1Fe alloy journal August 1997
Indentation of a Power Law Creeping Solid journal April 1993
Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs journal June 2017
Impression creep; a new creep test journal November 1977
Sound speeds in and mechanical properties of (U,Pu)O 2− x journal November 2017
Invited Article: Indenter materials for high temperature nanoindentation journal October 2013
Study of the formation of UO2-PuO2 solid solution by means of UO2-CeO2 simulate journal August 1986
Mechanical properties of (U,Ce)O2 with and without Nd or Zr journal August 2001
Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry journal April 2019
Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels journal April 2017
Indentation size effect in unirradiated and ion-irradiated 800H steel at high temperatures journal February 2018
3D fuel cracking modelling in pellet cladding mechanical interaction journal July 2008
Hot hardness and thermal conductivity of ThO2-PuO2 and ThO2-UO2 sintered pellets journal April 1989
Physical mechanism analysis of burnup actinide composition in light water reactor MOX fuel and its application to uncertainty evaluation journal July 2015
Nanoindentation testing of high burn-up fast reactor mixed oxide fuel journal June 2022
Experimental characterization and modelling of UO2 behavior at high temperatures and high strain rates journal January 2015
Elevated temperature creep of polycrystalline uranium dioxide: from microscopic mechanisms to macroscopic behaviour journal April 2002
Elevated temperature microcantilever testing of fresh U-10Mo fuel journal December 2019
An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments journal June 1992
Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering journal February 2021
Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA journal May 2020
Young's modulus evaluation of high burnup structure in UO2 with nanometer resolution journal September 2018
Nanoindentation studies of UO2 and (U,Ce)O2 journal November 2004
The compressive creep behavior of (U, Ce)O2 journal April 2007
Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering journal March 2020
Elevated Temperature Nanoindentation Creep Study of Plastically Deformed and Spark Plasma Sintered UO2 journal March 2021
Creep of single-crystal UO2 journal April 1966
Measurement of power-law creep parameters by instrumented indentation methods journal February 2013
Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products journal April 2020
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Microstructural evolution of uranium dioxide following compression creep tests: An EBSD and image analysis study journal January 2015
Fuel Performance of Light Water Reactors (Uranium Oxide and MOX) book January 2012
Effect of Nd and Pr addition on the thermal and mechanical properties of (U,Ce)O2 journal May 2009
The influence of stoichiometry on compression creep of uranium dioxide single crystals journal July 1972
The effect of aluminum additions on the oxidation resistance of U3Si2 journal June 2017
Thermodynamic assessment of the oxygen rich U–Ce–O system journal December 2015
An improved long-term nanoindentation creep testing approach for studying the local deformation processes in nanocrystalline metals at room and elevated temperatures journal April 2013
A direct comparison of high temperature nanoindentation creep and uniaxial creep measurements for commercial purity aluminum journal June 2016
High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2) journal October 2021
A new characterization approach for studying relationships between microstructure and creep damage mechanisms of uranium dioxide journal June 2016

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