DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Transient behavior of oxide fuels with controlled microstructure and Cr2O3 additive

Journal Article · · npj Materials Degradation

Abstract Microstructure and Cr 2 O 3 doping profoundly impact the thermal-mechanical properties and fracture of oxides fuels. It is a challenge to study the transient behavior of nuclear fuels under loss-of-coolant-event (LOCA). In this study, the crack behavior of UO 2 pellets with controlled grain structure and Cr 2 O 3 doping was tested with rapid power ramping (300−900 °C per min) mimicking a prototypical LOCA heating profile. Dense micron-sized UO 2 pellets display well-maintained integrity without cracking with the ramping up to 1500 °C at a heating rate of 8 °C per second. Fracture occurs in both pure and Cr 2 O 3 -doped dense nano-sized UO 2 pellets. The Cr 2 O 3 doped oxide fuel pellet with a larger grain size (~ 22.2 μm) displays the best performance under LOCA testing due to its highest thermal conductivity under high temperature. FEA calculations suggest a temperature gradient across the fuel pellet during transient testing, resulting in residual stress and cracking, which can be correlated with their thermal-mechanical properties.

Sponsoring Organization:
USDOE
Grant/Contract Number:
NONE; NE0009209
OSTI ID:
2403591
Journal Information:
npj Materials Degradation, Journal Name: npj Materials Degradation Journal Issue: 1 Vol. 8; ISSN 2397-2106
Publisher:
Nature Publishing GroupCopyright Statement
Country of Publication:
United Kingdom
Language:
English

References (35)

Rapid heating thermal shock study of ultra high temperature ceramics using an in situ testing method journal December 2017
Enhanced thermal shock and oxidation resistance of Si2BC3N ceramics through MWCNTs incorporation journal September 2018
Modification of YSZ fiber composites by Al2TiO5 fibers for high thermal shock resistance journal April 2022
Fission gas release and swelling in UO2 doped with Cr2O3 journal February 1980
UO2 properties affecting performance journal January 1972
Absolute determination of the thermal conductivity of the noble gases at room temperature up to 35 MPa journal February 1980
Microstructural evolution during charcoal carbonization by X-ray diffraction analysis journal January 2003
A review of the thermophysical properties of MOX and UO2 fuels journal December 2001
Effect of additives (Cr2O3, Al2O3, SiO2, MgO) on diffusional release of from UO2 fuels journal April 1998
On the theory of fission gas bubble evolution in irradiated UO2 fuel journal January 2000
The role of dopant charge state on defect chemistry and grain growth of doped UO2 journal May 2018
Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties journal June 2020
Transient testing of oxide fuels by spark plasma sintering and finite element analysis journal February 2024
Fracture properties of sintered UO2 ceramic pellets with duplex microstructure journal June 2007
Nuclear fuels – Present and future journal May 2009
High temperature chromium volatilization from Cr2O3 powder and Cr2O3-doped UO2 pellets in reducing atmospheres journal April 2012
Chromia doped UO2 fuel: Investigation of the lattice parameter journal May 2012
Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry journal April 2019
Fission gas diffusion and release for Cr 2 O 3 -doped UO 2 : From the atomic to the engineering scale journal March 2021
Phase-field simulations of fission gas bubbles in high burnup UO2 during steady-state and LOCA transient conditions journal December 2021
Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties journal December 2021
Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance journal February 2022
Application of BISON to UO2 MiniFuel fission gas release analysis journal July 2022
Thermal-shock experiments for separate-effects validation of UO2 fuel fracture models journal December 2022
Grain growth kinetics of the gamma phase metallic uranium journal February 2023
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties journal February 2023
Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient journal October 2023
Grain growth and microstructure evolution based mechanical property predicted by a modified Hall–Petch equation in hot worked Ni76Cr19AlTiCo alloy journal March 2014
Oxidation kinetics of SPS-densified U3Si2 fuels—Microstructure impact journal June 2022
Fracture Surface Energy of UO2and ThO2Containing Additives journal December 1980
Advanced Doped UO 2 Pellets in LWR Applications journal September 2006
A Critical Evaluation of Indentation Techniques for Measuring Fracture Toughness: I, Direct Crack Measurements journal September 1981
Grain growth and pore coarsening in dense nano‐crystalline UO 2+ x fuel pellets journal March 2017
An Assessment of the Fuel Pulverization Threshold During LOCA-Type Temperature Transients journal April 2015
SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4 report June 1995