Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation

Sweet, R. T.; George, N. M.; Maldonado, G. I.; Terrani, K. A.; Wirth, B. D.

doi:10.1016/j.nucengdes.2017.11.043

Title: Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation

Full Record
Other Related Research

Authors:: Sweet, R. T.; George, N. M.; Maldonado, G. I.; Terrani, K. A.; Wirth, B. D.

Publication Date:: Thu Mar 01 00:00:00 EST 2018

Sponsoring Org.:: USDOE

OSTI Identifier:: 1512356

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Name: Nuclear Engineering and Design Journal Volume: 328 Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Citation Formats


                    Sweet, R. T., George, N. M., Maldonado, G. I., Terrani, K. A., and Wirth, B. D. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation.  Netherlands: N. p., 2018. 
Web.  doi:10.1016/j.nucengdes.2017.11.043.

Copy to clipboard


                    Sweet, R. T., George, N. M., Maldonado, G. I., Terrani, K. A., & Wirth, B. D. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation.  Netherlands.  https://doi.org/10.1016/j.nucengdes.2017.11.043

Copy to clipboard


                    Sweet, R. T., George, N. M., Maldonado, G. I., Terrani, K. A., and Wirth, B. D. Thu .  
"Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation".  Netherlands.  https://doi.org/10.1016/j.nucengdes.2017.11.043.

Copy to clipboard


                    
@article{osti_1512356,

  title        = {Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation},

  author       = {Sweet, R. T. and George, N. M. and Maldonado, G. I. and Terrani, K. A. and Wirth, B. D.},

  abstractNote = {},

  doi          = {10.1016/j.nucengdes.2017.11.043},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 328,

  place        = {Netherlands},

  year         = {Thu Mar 01 00:00:00 EST 2018},

  month        = {Thu Mar 01 00:00:00 EST 2018}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Publisher's Version of Record
https://doi.org/10.1016/j.nucengdes.2017.11.043

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 16 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Fuel Performance Simulation of Iron-Chrome-Aluminum Cladding during Steady-State LWR Operation

Journal Article Sweet, R. T. ; Terrani, K. A. ; Wirth, B. D. ; ... - Transactions of the American Nuclear Society

During a severe accident scenario, such as a loss-of-coolant accident, a nuclear reactor may lose its capacity to cool its fuel. The fuel rod temperatures begin to increases, quickly reaching temperatures where the coolant begins to evaporate. This lowers the coolant level in the core and eventually uncovers the fuel. Without sufficient heat transfer from the fuel rods to the coolant, the temperature of the fuel and cladding will increase dramatically. In the case of traditional zirconium-based alloys, as the temperature of the cladding reaches ∼1200 deg. C the zirconium rapidly begins to oxidize with H{sub 2}O in the coolantmore »« less
Fuel performance analysis of FeCrAl cladding during LWR operation

Conference Sweet, R. T. ; George, N. M. ; Terrani, K. A. ; ...

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)more »« less
PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code

Journal Article Capps, Nathan ; Mai, Anh ; Kennard, Michael ; ... - Nuclear Engineering and Design

Not provided.
https://doi.org/10.1016/j.nucengdes.2018.03.045
Behavior of fission gas in LWR fuel during steady-state operating conditions

Conference Rest, J - Trans. Am. Nucl. Soc.; (United States)
Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties

Journal Article Gorton, Jacob P. ; Lee, Soon K. ; Lee, Youho ; ... - Nuclear Engineering and Design

In this paper we analyze the differences between previous transient critical heat flux (CHF) experiments using iron-chromium-aluminum (FeCrAl), Inconel 600, and stainless steel 316 (SS316) alloy test sections and best-estimate modeling results from widely-used nuclear engineering systems and subchannel analysis tools. FeCrAl is an Accident Tolerant Fuel (ATF) candidate cladding material. The thermal hydraulic performance and safety characteristics of FeCrAl are being evaluated to determine viability as a cladding material in Light Water Reactors (LWRs). In this study, the results of the CHF experiments conducted at atmospheric pressure and fixed inlet coolant temperature and mass flux are compared to modelsmore »« less
Cited by 8
https://doi.org/10.1016/j.nucengdes.2019.110295

Full Text Available

Similar Records