Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings
Abstract
The U.S. Department of Energy’s Accident Tolerant Fuel program is focused on extending the time for fuel failure during postulated severe accidents compared to the standard UO2-Zr alloy fuel system. This research investigates the feasibility of two different chromium-coated cladding concepts, one of which is zirconium-alloy based and the other is composite-SiC based. Both claddings had 50µm coatings, deducted from the base layer thicknesses. The claddings were reported on, using the multi- physics fuel performance tool BISON, under steady-state PWR operating conditions as well as two transients: power ramp and a loss-of-coolant accident (LOCA). The chromium-coated claddings showed comparable thermo-mechanical performance to the reference Zircaloy-4 cladding. As chromium is reported to provide an order of magnitude improvement in oxidation resistance, it is expected to be a better alternative in accident scenarios. Simulation results for both concepts call for further experimental investigation as well as modeling of beyond design-basis accidents.
- Authors:
-
[2];
[2];
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1550920
- Alternate Identifier(s):
- OSTI ID: 1582698
- Report Number(s):
- INL-JOU-18-50119-Rev000
Journal ID: ISSN 0306-4549
- Grant/Contract Number:
- AC07-05ID14517; NE0008416
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Annals of Nuclear Energy (Oxford)
- Additional Journal Information:
- Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 120; Journal Issue: C; Journal ID: ISSN 0306-4549
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Accident Tolerant Fuel; Chromium; Silicon Carbide; Cladding; Nuclear Fuel; Bison
Citation Formats
Wagih, Malik, Spencer, Benjamin, Hales, Jason, and Shirvan, Koroush. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. United States: N. p., 2018.
Web. doi:10.1016/j.anucene.2018.06.001.
Wagih, Malik, Spencer, Benjamin, Hales, Jason, & Shirvan, Koroush. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. United States. https://doi.org/10.1016/j.anucene.2018.06.001
Wagih, Malik, Spencer, Benjamin, Hales, Jason, and Shirvan, Koroush. Thu .
"Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings". United States. https://doi.org/10.1016/j.anucene.2018.06.001. https://www.osti.gov/servlets/purl/1550920.
@article{osti_1550920,
title = {Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings},
author = {Wagih, Malik and Spencer, Benjamin and Hales, Jason and Shirvan, Koroush},
abstractNote = {The U.S. Department of Energy’s Accident Tolerant Fuel program is focused on extending the time for fuel failure during postulated severe accidents compared to the standard UO2-Zr alloy fuel system. This research investigates the feasibility of two different chromium-coated cladding concepts, one of which is zirconium-alloy based and the other is composite-SiC based. Both claddings had 50µm coatings, deducted from the base layer thicknesses. The claddings were reported on, using the multi- physics fuel performance tool BISON, under steady-state PWR operating conditions as well as two transients: power ramp and a loss-of-coolant accident (LOCA). The chromium-coated claddings showed comparable thermo-mechanical performance to the reference Zircaloy-4 cladding. As chromium is reported to provide an order of magnitude improvement in oxidation resistance, it is expected to be a better alternative in accident scenarios. Simulation results for both concepts call for further experimental investigation as well as modeling of beyond design-basis accidents.},
doi = {10.1016/j.anucene.2018.06.001},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 120,
place = {United States},
year = {Thu Jun 14 00:00:00 EDT 2018},
month = {Thu Jun 14 00:00:00 EDT 2018}
}
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Works referencing / citing this record:
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