Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance-Reference-Cited by-同舟云学术

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Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance

Published:2018-03 Issue:2 Volume:50 Page:229-236
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Ševeček Martin^ORCID,Gurgen Anil^ORCID,Seshadri Arunkumar,Che Yifeng,Wagih Malik,Phillips Bren^ORCID,Champagne Victor,Shirvan Koroush

Funder

US Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. CEA studies on advanced nuclear fuel claddings for enhanced accident tolerant LWRs fuel (LOCA and beyond LOCA conditions);Brachet,2015

2. Development status of accident-tolerant fuel for light water reactors in Korea;Kim;Nucl. Eng. Technol.,2016

3. Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors;Maier;JOM,2018

4. Development of chromium and chromium nitride coated cladding for VVER reactors;Krejci,2017

5. Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air;Kuprin;J. Nucl. Mater.,2015

Cited by 122 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. Quantifying cracking and strain localisation in a cold spray chromium coating on a zirconium alloy substrate under tensile loading at room temperature;Journal of Nuclear Materials;2024-04

2. Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere;Journal of Nuclear Materials;2024-02

3. Elucidating changes in thermal creep strain rate of Cr-coated Zr-Nb alloy Accident Tolerant Fuel (ATF) cladding via experiment and mechanical analysis;Journal of Nuclear Materials;2024-02

4. Unveiling fracture mechanics of a curved coating/substrate system by combined digital image correlation and numerical finite element analyses;Engineering Fracture Mechanics;2024-02

5. Enhancing the oxidation behaviors of Zr alloys for nuclear fuel cladding using nanolamellar Cr/CrN coating;Corrosion Science;2024-02

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