Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux-Reference-Cited by-同舟云学术

Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux

Published:2020-06 Issue: Volume:362 Page:110581
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ali Amir^ORCID,Kim Hyun-Gil,Hattar Khalid,Briggs Samuel,Jun Park Dong,Hwan Park Jung,Lee Youho

Funder

Nuclear Energy University Program

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference45 articles.

1. Ali, A.F., El-Genk, M.S., 2013. An Investigation of the Effect of Inclination on Critical Heat Flux of PF-5060 Dielectric Liquid on Microporous Copper Surfaces. ASME IMECE2013, San Diego, California, paper#IMECE2013-65503.

2. Surface wettability and pool boiling critical heat flux of accident tolerant fuel cladding-FeCrAl Alloys;Ali;Nucl. Eng. Des.,2018

3. Ali, A., Liu, M., Brown, N., Terrani, K., Blandford, E., 2017. Surface wettability measurements of FeCrAl Alloys under LWR environments. The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi’an, China.

4. American Society of Testing Materials (ASTM), 2008. Standard Testing Method for Surface Wettability and Absorbency of Sheeted Materials Using an Automated Contact Angle. Designation: D 5725 – 99.

5. American Society of Testing Materials (ASTM), 2013. Standard Practice for Surface Wettability of Coatings, Substrates, and Pigments by Advancing Contact Angle Measurement. Designation: D7334 – 08.

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1. Effect of ultrasonic field on pool boiling heat transfer to Al₂O₃ nanofluid on ribbed surfaces;Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy;2024-08-01

2. The effect of ramp heating on the microstructure and surface chemistry of APMT FeCrAl alloy;Nuclear Materials and Energy;2024-03

3. Calculations and analysis of n+ ⁵² Cr reactions below 20 MeV;Journal of Nuclear Science and Technology;2024-01-04

4. Experimental investigations on the thermal performance of ultrasonic field in pool boiling on rib surfaces;Heat and Mass Transfer;2023-10-18

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