Thermal and fluid analysis of dry cask storage containers over multiple years of service-Reference-Cited by-同舟云学术

Thermal and fluid analysis of dry cask storage containers over multiple years of service

Published:2018-02 Issue: Volume:112 Page:132-142
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Wu Yongjia,Klein Jackson,Zhou Hanchen,Zuo Lei

Funder

DOE United States

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference36 articles.

1. Adkins, H.E., 2012. Modeling Used Fuel Storage Temperatures. Presentation to the US Nuclear Waste Technical Review Board.

2. World Nuclear Association, 2017. Nuclear Fuel and its Fabrication.

3. Bahney, R., Lotz, T., 1996. Spent nuclear fuel effective thermal conductivity report. Prepared for the US DOE, Yucca Mountain Site Characterization Project Office by TRW Environmental Safety Systems Inc, July 11.

4. Convection Heat Transfer;Bejan,2013

5. CFD analyses of the TN-24p PWR spent fuel storage cask, ASME 2012 Pressure Vessels and Piping Conference;Brewster;Am. Soc. Mech. Eng.,2012

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