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

Title: Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2000097
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 585 Journal Issue: C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (33)

A phase-field model with irradiation-enhanced diffusion for constituent redistribution in U-10wt%Zr metallic fuels journal September 2022
Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction journal June 2023
Fuels for sodium-cooled fast reactors: US perspective journal September 2007
Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9 journal October 2017
A study of constituent redistribution in U–Zr fuels using quantitative phase-field modeling and sensitivity analysis journal September 2019
Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel journal December 1993
Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations journal October 2018
Modeling of Fission-Gas-Induced Swelling of Nuclear Fuels* book February 2012
TREAT Restart Project journal April 2019
FIPD: EBR-II Fuels Irradiation & Physics Database – FY19 Updates report September 2019
Atomistic mechanisms of morphological evolution and segregation in U-Zr alloys journal August 2016
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins journal May 2016
Calorimetric Study of Phase Stability and Phase Transformation in U-xZr (x = 2, 5, 10 wt pct) Alloys journal September 2015
Postirradiation characterization of palladium as an additive for fuel cladding chemical interaction mitigation in metallic fuel journal January 2022
Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient journal February 2021
Thermodynamic modeling of the U–Zr system – A revisit journal November 2013
α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel journal December 2020
Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT) journal February 2020
Phase identification and morphology in rolled and annealed U-22.5at.%Zr foils journal November 2021
The formation mechanism of the Zr rind in U-Zr fuels journal December 2022
Modeling the behavior of metallic fast reactor fuels during extended transients journal September 1993
Modeling constituent redistribution in U–Pu–Zr metallic fuel using the advanced fuel performance code BISON journal May 2015
The U-Zr (Uranium-Zirconium) system journal April 1989
Postirradiation examination on metallic fuel in the AFC-2 irradiation test series journal October 2018
The porosity dependence of the thermal conductivity for nuclear fuels journal April 1973
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing journal October 2020
Formation of face-centered-cubic zirconium by mechanical attrition journal November 2002
Thermophysical investigations of the uranium–zirconium alloy system journal October 2014
Microstructure Evolution of U–Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U–10Zr (wt. %) journal February 2021
In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing journal March 2020
Mechanistic materials modeling for nuclear fuel performance journal July 2017
Swelling behavior of U-Pu-Zr fuel journal February 1990
Verification of the BISON fuel performance code journal September 2014