Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas-Reference-Cited by-同舟云学术

Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas

Published:2019-10 Issue: Volume:132 Page:108-118
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Yoo Hee Sang,Yoo Seung Hun,Kim Eung Soo^ORCID

Funder

National Research Foundation of Korea

Ministry of Science ICT & Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. CFD analyses of the TN-24P PWR spent fuel storage cask;Brewster,2012

2. Bunn, Matthew G., et al., 2001. Interim Storage of Spent Nuclear Fuel: A Safe, Flexible, and Cost-Effective Approach to Spent Fuel Management.

3. Thermal conductivity of gas mixtures;Cheung;AIChE J.,1962

4. Creer, J.M., et al. 1987. The TN-24P PWR spent-fuel storage cask: Testing and analyses: Interim report. No. EPRI-NP-5128. Pacific Northwest Lab., Richland, WA (USA); Virginia Electric and Power Co., Richmond (USA); Idaho National Engineering Lab., Idaho Falls (USA); Electric Power Research Inst., Palo Alto, CA (USA).

5. Noble gas binary mixtures for gas-cooled reactor power plants;El-Genk;Nucl. Eng. Des.,2008

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