Results 41 to 50 of about 248 (163)

Chromium Coatings Applied to Zr Alloy Claddings by Cathodic Arc Ion Plating: Effect of Nitrogen Inclusion on Limiting Columnar Defects

Advanced Engineering Materials, Volume 26, Issue 20, October 2024.
The nitrogen incorporation effectively mitigates columnar defects in chromium‐based coatings on the Zr alloy claddings. The important significance of chromium‐based coatings is that they are suitable material candidates for accident‐tolerant fuel cladding of nuclear fuel rods.
Hae Won Yoon, Yuri Choi, Kuk Hyun Yeo, Sang Gweon Kim, Yong Ki Cho   +4 more
wiley   +1 more source

Abstracts

, 2021
Research and Practice in Thrombosis and Haemostasis, Volume 5, Issue S2, October 2021.
wiley   +1 more source

Feasibility study for the criticality calculations of the LEU+ with ATF fuels

Nuclear Engineering and Technology
This study evaluates the criticality safety of Accident Tolerant Fuel (ATF) and LEU+ (5–10 wt% U-235) in the APR-1400 spent fuel pool (Region 1) and new fuel storage vault (NFSV) using SCALE 6.3.1's CSAS6/KENO-VI module.
Keon Il Cha, Seok Geun Cho, Kyoon Ho Cha
doaj   +1 more source

LEU+ loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme

Nuclear Engineering and Technology, 2023
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU + has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4–5 w/o UO2 fuel.
Husam Khalefih, Taesuk Oh, Yunseok Jeong, Yonghee Kim   +3 more
doaj   +1 more source

EHA2021 Virtual Congress Abstract Book

, 2021
HemaSphere, Volume 5, Issue S2, June 2021.
wiley   +1 more source

Thermal diffusivity of ATF cladding materials using laser flash technique

Acta Polytechnica CTU Proceedings
Accident tolerant fuel (ATF) cladding materials are designed to improve the fuel behavior in normal operation while further enhancing the material performance in accidental scenarios.
Jakub Vrzal, Martin Ševeček, Luka Vlahovic   +2 more
doaj   +1 more source

Breaking Boundaries with Ceramic Matrix Composites: A Comprehensive Overview of Materials, Manufacturing Techniques, Transformative Applications, Recent Advancements, and Future Prospects

Advances in Materials Science and Engineering, Volume 2024, Issue 1, 2024.
Ceramic matrix composites (CMCs) are a category of advanced materials which have gained significant interest recently due to their remarkable mechanical and thermal characteristics. These composites are composed of ceramic fibers, particles, or other types of ceramics incorporated in a ceramic matrix and have shown the capability to be implemented in ...
Adib Bin Rashid, Mahima Haque, S. M. Mohaimenul Islam, K. M. Rafi Uddin Labib, Pavel Chowdhury, Rajesh Kannan A   +5 more
wiley   +1 more source

Abstracts of the 79th Annual Meeting of the Japanese Cancer Association; 2020 Oct 1‐3; Hiroshima, Japan as Cancer Science, Supplement 1, Vol 112 (2021)

, 2021
Cancer Science, Volume 112, Issue S1, Page 1-1072, February 2021.
wiley   +1 more source

Modelling of fission gas release in UO2 doped fuel using transuranus code

Acta Polytechnica CTU Proceedings, 2022
The expected benefits from Cr-doped fuel are improved retention of fission gases within the pellets due to its large grain size. To demonstrate this, several experiments have been carried out by Halden reactor and Studsvik.
Jheffry Gonzalez, Martin Ševecek
doaj   +1 more source

Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
Nuclear accidents, such as the Fukushima nuclear accident, have highlighted the necessity for accident‐tolerant fuel (ATF) cladding. Previous studies focused on coating the outside of Zr alloy currently used in nuclear reactors with an oxidation‐resistant material in a vacuum environment.
Jeong-Hye Jo, Ji-Hyeok Choi, Jong Woo Kim, Dong-Joo Kim, Young Soo Yoon, Hock Jin Quah   +5 more
wiley   +1 more source