Modeling of constituent redistribution in U-Pu-Zr metallic fuel.
Journal Article
·
· J. Nucl. Mater.
A computer model was developed to analyze constituent redistribution in U-Pu-Zr metallic nuclear fuels. Diffusion and thermochemical properties were parametrically determined to fit the postirradiation data from a fuel test performed in the Experimental Breeder Reactor II (EBR-II). The computer model was used to estimate redistribution profiles of fuels proposed for the conceptual designs of small modular fast reactors. The model results showed that the level of redistribution of the fuel constituents of the designs was similar to the measured data from EBR-II.
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 953449
- Report Number(s):
- ANL/NE/JA-57129
- Journal Information:
- J. Nucl. Mater., Journal Name: J. Nucl. Mater. Journal Issue: 1-2 ; Dec. 1, 2006 Vol. 359; ISSN 0022-3115; ISSN JNUMAM
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content
Constituent migration model for fast reactor U-Pu-Zr metallic fuel
Constituent migration model for U-Pu-Zr metallic fast reactor fuel
Journal Article
·
Thu Sep 16 00:00:00 EDT 2021
· Journal of Nuclear Materials
·
OSTI ID:1831652
Constituent migration model for fast reactor U-Pu-Zr metallic fuel
Conference
·
Mon Dec 31 23:00:00 EST 1990
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5981231
Constituent migration model for U-Pu-Zr metallic fast reactor fuel
Journal Article
·
Fri Oct 01 00:00:00 EDT 1993
· Nuclear Technology; (United States)
·
OSTI ID:5889761