Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications-Reference-Cited by-同舟云学术

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Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications

Published: Issue: Volume: Page:330-330-17
ISSN:
Container-title:Zirconium in the Nuclear Industry: Fourteenth International Symposium
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Author:

Yueh HK,Kesterson RL,Comstock RJ,Shah HH,Colburn DJ,Dahlback M,Hallstadius L

Publisher

ASTM International

Cited by 20 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Study on oxidation behaviors of Zr–Sn–Nb alloy in water steam at 1250 °C;AIP Advances;2023-12-01

2. Advanced PWR Cladding Development through Extensive In-Reactor Testing;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01

3. E110opt Fuel Cladding Corrosion under PWR Conditions;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01

4. STEM/EDS and APT study on the microstructure and microchemistry of neutron irradiated ZIRLOTM;Journal of Nuclear Materials;2023-01

5. Boiling heat transfer experiments under power transients for LWRs: A review study;Progress in Nuclear Energy;2021-11

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