skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Characterization of phases formed between U–Pu–Mo fuels and Fe–12Cr cladding

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1252498
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 464 Journal Issue: C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 3 works
Citation information provided by
Web of Science

References (11)

Equilibrium phase relations in the U–Zr–Fe ternary system journal November 1999
Thermodynamic evaluation of the quaternary U–Pu–Zr–Fe system – assessment of cladding temperature limits of metallic fuel in a fast reactor journal April 2001
Phase relations in the quaternary Fe–Pu–U–Zr system journal July 2002
Modeling of constituent redistribution in U–Pu–Zr metallic fuel journal December 2006
Thermodynamic assessment of the Fe–U, U–Zr and Fe–U–Zr systems journal June 1998
Phase characteristics of a number of U–Pu–Am–Np–Zr metallic alloys for use as fast reactor fuels journal January 2010
Migration of minor actinides and lanthanides in fast reactor metallic fuel journal July 2009
X-Ray Analysis of Chromium-Molybdenum and Chromium-Tungsten Alloys journal February 1947
Density-functional study of U–Mo and U–Zr alloys journal July 2011
Modeling of Ni–Cr–Mo based alloys: Part I—phase stability journal March 2006
The plutonium - uranium system journal October 1959

Similar Records

Characterization of phases formed between U-Pu-Mo alloys and Fe-12Cr cladding
Journal Article · Mon Sep 01 00:00:00 EDT 2014 · Journal of Nuclear Materials · OSTI ID:1252498

TEM examination of phases formed between U–Pu–Zr fuel and Fe
Journal Article · Tue Dec 01 00:00:00 EST 2015 · Journal of Nuclear Materials · OSTI ID:1252498

Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding
Journal Article · Wed Oct 20 00:00:00 EDT 2021 · Journal of Nuclear Materials · OSTI ID:1252498

Related Subjects