Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution-Reference-Cited by-同舟云学术

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Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution

Published:2009-08 Issue:8 Volume:46 Page:836-845
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

YANG Yong Sik,SHIN Chang Hwan,CHUN Tae Hyun,SONG Kun Woo

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/18811248.2007.9711593

Reference15 articles.

1. MIT-NFC-PR-082;Kazimi M. S.,2006

2. MIT-NFC-TR-067;Yuan Y.,2004

3. Irradiation Behavior of Large Grain UO2Fuel Rod by Active Powder

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1. Neutronic analysis of different sandwich cladding material options for (Th-233U-235U)O2 annular fuel in advanced PWR assembly;Interactions;2024-08-24

2. Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study;Nuclear Energy and Technology;2024-08-02

3. Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle;Annals of Nuclear Energy;2023-12

4. Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly;Nuclear Engineering and Design;2023-12

5. Transient fuel performance analysis of UO2–BeO fuel with composite SiC coated with Cr cladding based on multiphysics method;Nuclear Science and Techniques;2023-12

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