Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials-Reference-Cited by-同舟云学术

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Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials

Published:2021-02 Issue: Volume:185 Page:116347
ISSN:1359-4311
Container-title:Applied Thermal Engineering
language:en
Short-container-title:Applied Thermal Engineering

Author:

Lee Donghwi,Elward Barret,Brooks Paul,Umretiya Rajnikant,Rojas Jessika,Bucci Matteo,Rebak Raul B.,Anderson Mark

Funder

Office of Nuclear Energy

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Energy Engineering and Power Technology

Reference64 articles.

1. WNA -World Nuclear Association, Nuclear Power Today | Nuclear Energy - World Nuclear Association, 2016. (2016). https://doi.org/10.1109/ICIECS.2010.5677899.

2. Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology;Zhang;Ann. Nucl. Energy.,2019

3. DNB type critical heat flux prediction in rod bundles with simplified grid spacer based on Liquid Sublayer Dryout model;Zhao;Nucl. Eng. Des.,2019

4. Critical heat flux experiments and a post-CHF heat transfer analysis using 2D inverse heat transfer;Duarte;Nucl. Eng. Des.,2018

5. Presentation and comparison of experimental critical heat flux data at conditions prototypical of light water small modular reactors;Greenwood;Nucl. Eng. Des.,2017

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1. Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond;Alexandria Engineering Journal;2024-12

2. Chloride-induced stress corrosion cracking in Austenitic steels for SNF storage canisters - Recent understanding and advances in mitigation and repair;Journal of Nuclear Materials;2024-08

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

4. Numerical simulation prediction of critical heat flux for 5 × 5 rod bundle with multiple grid spacers and different cladding materials;Annals of Nuclear Energy;2024-06

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