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

doi:10.1016/j.nucengdes.2019.110295

Title: 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

Full Record
Other Related Research

Authors:: Gorton, Jacob P.; Lee, Soon K.; Lee, Youho; Brown, Nicholas R.

Publication Date:: 2019-11-01

Sponsoring Org.:: USDOE

OSTI Identifier:: 1558678

Grant/Contract Number:: 17-12688

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Name: Nuclear Engineering and Design Journal Volume: 353 Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Citation Formats


                    Gorton, Jacob P., Lee, Soon K., Lee, Youho, and Brown, Nicholas R. 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.  Netherlands: N. p., 2019. 
        Web.  doi:10.1016/j.nucengdes.2019.110295.

Copy to clipboard


                    Gorton, Jacob P., Lee, Soon K., Lee, Youho, & Brown, Nicholas R. 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.  Netherlands.  doi:10.1016/j.nucengdes.2019.110295.

Copy to clipboard


                    Gorton, Jacob P., Lee, Soon K., Lee, Youho, and Brown, Nicholas R. Fri .  
        "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".  Netherlands.  doi:10.1016/j.nucengdes.2019.110295.

Copy to clipboard


                    
@article{osti_1558678,

  title        = {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},

  author       = {Gorton, Jacob P. and Lee, Soon K. and Lee, Youho and Brown, Nicholas R.},

  abstractNote = {},

  doi          = {10.1016/j.nucengdes.2019.110295},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 353,

  place        = {Netherlands},

  year         = {2019},

  month        = {11}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Publisher's Version of Record
DOI: 10.1016/j.nucengdes.2019.110295

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 2 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:

Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel

Journal Article Lee, Soon ; Liu, Maolong ; Brown, Nicholas ; ... - International Journal of Heat and Mass Transfer

Steady and transient (with a heating rate of 685?/s) internal-flow CHF (Critical Heat Flux) experiments were conducted under atmospheric pressure at a fixed inlet temperature (40? or 60?) and mass flow (300kg/m²s) on Fe-13Cr-6Al alloy, Inconel 600 and Zircaloy-4 tube samples. Multiple experiments were repeated on the same specimen to investigate the effect of surface characteristic changes (i.e., roughness, wettability, and oxide scale morphology) on the occurrence of CHF. Despite notable changes of wettability, roughness, and oxide layer characteristics on samples that had already been subjected to CHF, measured flow CHF remained unchanged throughout repeated experiments for tested materials. This demonstrates that the surface effects on flow CHF are limited in the test conditions. In the steady-state flow boiling condition, Fe-13Cr-6Al alloy demonstrated a 22% and 14% increase in CHF compared to Zircaloy-4 and Inconel 600, respectively. Compared to the 2006 Groeneveld CHF lookup table, Fe-13Cr-6Al alloy gives a 13% increase in the tested flow boiling condition. Material properties are considered primarily responsible for the observed CHF differences among the tested materials. The surface thermal economy parametermore »« less
Cited by 14
DOI: 10.1016/j.ijheatmasstransfer.2018.11.141

Full Text Available
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions

Journal Article Brown, Nicholas ; Garrison, Ben ; Lowden, Rick R. ; ... - Journal of Nuclear Materials
DOI: 10.1016/j.jnucmat.2020.152352
Steam Oxidation, Burst and Critical Heat Flux Testing of FeCrAl Cladding in the Severe Accident Test Station

Technical Report Pint, Bruce A.

Since August 2011, Oak Ridge National Laboratory (ORNL) has been evaluating the steam oxidation resistance of a wide range of materials to identify a potential accident tolerant fuel (ATF) cladding [1-14]. The primary goal of an ATF cladding is to enhance safety margins in light water reactors (LWR) during beyond design basis accident scenarios (such as the nuclear accident at Fukushima Daiichi in March 2011) without requiring changes to the reactor design or fuel enrichment, or significantly affecting reactor economics during normal operation.
DOI: 10.2172/1474586

Full Text Available
Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys

Journal Article Ali, Amir F. ; Gorton, Jacob P. ; Brown, Nicholas R. ; ... - Nuclear Engineering and Design
DOI: 10.1016/j.nucengdes.2018.08.024
STEAM OXIDATION, BURST AND CRITICAL HEAT FLUX TESTING OF COMMERCIAL FECRAL CLADDING

Conference Pint, Bruce A. ; Baldesberger, Lucas ; Kane, Kenneth

A new accident tolerant Fe-12Cr-6Al-2Mo-0.2Si-0.03Y (C26M) fuel cladding was developed in response to the nuclear accident in Japan. Now that large quantities of commercial tubing are being fabricated, integral testing has expanded to include isothermal and non-isothermal steam oxidation testing, loss of coolant accident (LOCA) burst testing and critical heat flux (CHF) behavior. The oxidation behavior is being compared to other FeCrAl compositions and includes protective alumina scale formation during ramp testing at up to 11°C/min to 1475°C. Using standard LOCA conditions of 5°C/s heating in steam, burst testing was conducted with hoop stresses of 20-110 MPa and indicated highermore »« less
Full Text Available

Similar Records