Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux-Reference-Cited by-同舟云学术

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Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux

Published:2019-12-10 Issue:2 Volume:206 Page:339-346
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Lee Soon K.¹²,Liu Maolong²,Brown Nicholas R.¹^ORCID,Terrani Kurt A.³,Lee Youho⁴^ORCID

Affiliation:

1. University of Tennessee, 1412 Circle Drive, Knoxville, Tennessee 37996

2. University of New Mexico, 1 University of New Mexico, Albuquerque, New Mexico 87131

3. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37831

4. Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, Korea

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2019.1670010

Reference15 articles.

1. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

2. M. B. CINBIZ et al. “Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts Under RIA,” ORNL/LTR-2018/521, Oak Ridge National Laboratory (2018).

3. J. J. POWERS et al. “Report on Reactor Physics Assessment of Candidate Accident Tolerant Fuel Cladding Materials in LWRs,” ORNL/TM-2015/415, Oak Ridge National Laboratory (2015).

4. Experimental study of saturated pool boiling heat transfer with FeCrAl- and Cr-layered vertical tubes under atmospheric pressure

5. Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys

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1. Experimental investigations of material-conjugated subcooled flow boiling;Progress in Nuclear Energy;2024-09

2. Time in DNB experimental study on Cr coated zircaloy cladding;Applied Thermal Engineering;2024-07

3. Steady-state and power transient critical heat flux experiments of FeCrAl and Zircaloy claddings under saturated pool boiling;Nuclear Engineering and Design;2023-08

4. Experimental Investigation of Critical Heat Flux;2023 23rd International Scientific Conference on Electric Power Engineering (EPE);2023-05-24

5. Development of experimental and computational frameworks to predict subcooled flow boiling in the LANL Isotope Production Facility;International Journal of Heat and Mass Transfer;2023-04

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