Development of deformation model for simulation of mechanical behaviors of coated-cladding-Reference-Cited by-同舟云学术

Development of deformation model for simulation of mechanical behaviors of coated-cladding

Published:2018-06-18 Issue:10 Volume:55 Page:1225-1234
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kim Dong-Hyun¹²,Kim Hyo chan¹,Shin Chang hwan¹,Kim Hak-Sung²³

Affiliation:

1. Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute, Yuseong-gu, Korea

2. Department of Mechanical Engineering, The Hanyang University, Seongdong-gu, Korea

3. Institute of Nano Science and Technology, The Hanyang University, Seongdong-gu, Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2018.1486243

Reference15 articles.

1. KAERI’s Development of LWR Accident-Tolerant Fuel

2. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings

3. Geelhood KJ, Luscher WG, Beyer CE, et al. FRAPTRAN 1.4: a computer code for the transient analysis of oxide fuel rods. Richland (WA): Pacific Northwest National Laboratory, US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research; 2011. (NUREG/CR-7023, 1).

Cited by 3 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. Interface stability and microstructural evolution of the (Cr/CrN)24-coated zirconium alloy under different thermal shock temperatures;Surface and Coatings Technology;2022-01

2. Microstructure, high-temperature corrosion and steam oxidation properties of Cr/CrN multilayer coatings prepared by magnetron sputtering;Corrosion Science;2021-10

3. Development of FRACAS-CT module with FRAPCON4.0P01 for simulation of mechanical behaviors for accident-tolerant fuel cladding in a reactor;Journal of Nuclear Science and Technology;2019-06-03