Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks-Reference-Cited by-同舟云学术

Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks

Published:2014-09 Issue: Volume:71 Page:427-435
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Kim Hyungjin,Kwon Oh Joon,Kang Gyeong-Uk,Lee Dong-Gyu

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. ANSYS Inc., 2013. FLUENT Tutorial Guide.

2. Babcock & Wilcox Fuel Company, 1991. BR-100 100-ton Rail/Barge Spent Fuel Shipping Cask. No. 51-1203400-01.

3. Bahney, R.H., Lotz, T.L., 1996. Spent nuclear fuel effective thermal conductivity report. BBA000000-01717-5705-00010 Rev00, US Department of Energy.

4. Bucholz, J.A., 1983. Scoping design analyses for optimized shipping casks containing 1-, 2-, 3-, 5-, 7-, or 10-Year-Old PWR spent fuel. Appendix J, ORNL/CSD/TM-149, Oak Ridge National Laboratory.

5. CRWMS M&O. Determination of PWR SNF Effective Conductivity. DI Number:BBA000000-01717-0200-00006 Rev 1.

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