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Title: Fuel performance analysis of FeCrAl cladding during LWR operation

Abstract

This work focuses on modeling the integral thermo-mechanical performance of FeCrAl cladded fuel during normal operation in light-water reactors. Preliminary analysis has been performed to assess FeCrAl alloys (namely Alkrothal 720 and APMT) as a suitable fuel cladding replacement for Zr-alloys, using the MOOSE-based, finite-element fuel performance code BISON. These simulations identify the effects of the mechanical-stress and irradiation responses of FeCrAl and provide a comparison with Zr-alloys. In comparing these clad materials, fuel rods have been simulated for normal reactor operation and simple steady-state operation. Normal reactor operating conditions target the cladding performance over the rod lifetime (∼4 cycles) for the highest-power rod in the highest-power fuel assembly under reactor power maneuvering. The power histories and axial temperature profiles input into BISON were generated from a neutronics study on full-core reactivity equivalence for FeCrAl using the 3D full core simulator NESTLE. Evolution of the FeCrAl cladding behavior over time is evaluated by using steady-state operating conditions such as a simple axial power profile, a constant cladding surface temperature, and a constant fuel power history. The fuel rod designs and operating conditions used are based off the Peach Bottom BWR and design consideration was given to minimize the neutronic penaltymore » of the FeCrAl cladding by changing fuel enrichment and cladding thickness. (authors)« less

Authors:
;  [1];  [2];  [1];  [3]
  1. Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37916 (United States)
  2. Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States)
  3. (United States)
Publication Date:
Research Org.:
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22765228
Resource Type:
Conference
Resource Relation:
Conference: TOP FUEL 2016: LWR fuels fuels with enhanced safety and performance, Boise, ID (United States), 11-15 Sep 2016; Other Information: Country of input: France; 7 refs.; Related Information: In: TOP FUEL 2016 Proceedings| 1670 p.
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 42 ENGINEERING; B CODES; BWR TYPE REACTORS; CLADDING; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; ENRICHMENT; FINITE ELEMENT METHOD; FUEL ASSEMBLIES; FUEL RODS; NUCLEAR FUELS; REACTOR OPERATION; SIMULATORS; STEADY-STATE CONDITIONS; STRESSES; THICKNESS; THREE-DIMENSIONAL CALCULATIONS; ZIRCONIUM ALLOYS

Citation Formats

Sweet, R. T., George, N. M., Terrani, K. A., Wirth, B. D., and Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831. Fuel performance analysis of FeCrAl cladding during LWR operation. United States: N. p., 2016. Web.
Sweet, R. T., George, N. M., Terrani, K. A., Wirth, B. D., & Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831. Fuel performance analysis of FeCrAl cladding during LWR operation. United States.
Sweet, R. T., George, N. M., Terrani, K. A., Wirth, B. D., and Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831. Fri . "Fuel performance analysis of FeCrAl cladding during LWR operation". United States.
@article{osti_22765228,
title = {Fuel performance analysis of FeCrAl cladding during LWR operation},
author = {Sweet, R. T. and George, N. M. and Terrani, K. A. and Wirth, B. D. and Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831},
abstractNote = {This work focuses on modeling the integral thermo-mechanical performance of FeCrAl cladded fuel during normal operation in light-water reactors. Preliminary analysis has been performed to assess FeCrAl alloys (namely Alkrothal 720 and APMT) as a suitable fuel cladding replacement for Zr-alloys, using the MOOSE-based, finite-element fuel performance code BISON. These simulations identify the effects of the mechanical-stress and irradiation responses of FeCrAl and provide a comparison with Zr-alloys. In comparing these clad materials, fuel rods have been simulated for normal reactor operation and simple steady-state operation. Normal reactor operating conditions target the cladding performance over the rod lifetime (∼4 cycles) for the highest-power rod in the highest-power fuel assembly under reactor power maneuvering. The power histories and axial temperature profiles input into BISON were generated from a neutronics study on full-core reactivity equivalence for FeCrAl using the 3D full core simulator NESTLE. Evolution of the FeCrAl cladding behavior over time is evaluated by using steady-state operating conditions such as a simple axial power profile, a constant cladding surface temperature, and a constant fuel power history. The fuel rod designs and operating conditions used are based off the Peach Bottom BWR and design consideration was given to minimize the neutronic penalty of the FeCrAl cladding by changing fuel enrichment and cladding thickness. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {7}
}

Conference:
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