Development of FRACAS-CT module with FRAPCON4.0P01 for simulation of mechanical behaviors for accident-tolerant fuel cladding in a reactor
Author:
Affiliation:
1. Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute, Daejeon, Korea
2. Department of Mechanical Engineering, Hanyang University, Seoul, Korea
3. Institute of Nano Science and Technology, Hanyang University, Seoul, Korea
Funder
National Research Foundation of Korea
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1624653
Reference19 articles.
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2. Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications
3. Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions
4. Neutronic design and evaluation of a PWR fuel assembly with accident tolerant-Fully Ceramic Micro-Encapsulated (AT-FCM) fuel
5. Carpenter D, Ahn K, Kao S, et al. Assessment of silicon carbide cladding for high performance light water reactors. Nuclear Fuel Cycle Program (CANES Reports). Center for Advanced Nuclear Energy Systems (CANES), Massachusetts Institute of Technology (MIT); 2007.
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