Safety Assessment of SiC Cladding Oxidation under Loss-of-Coolant Accident Conditions in Light Water Reactors-Reference-Cited by-同舟云学术

Safety Assessment of SiC Cladding Oxidation under Loss-of-Coolant Accident Conditions in Light Water Reactors

Published:2013-08 Issue:2 Volume:183 Page:210-227
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Lee Youho¹,McKrell Thomas J.¹,Yue Chao¹,Kazimi Mujid S.¹

Affiliation:

1. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering 77 Massachusetts Avenue, Cambridge, Massachusetts 02139-4307

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT12-122

Reference37 articles.

1. P. D. PARSONS et al. “The Deformation, Oxidation and Embrittlement of PWR Fuel Cladding in a Loss-of-Coolant Accident: A State-of-the-Art Report,” CSNI Report 129 (Dec. 1986).

2. Thermodynamic analysis of the high-temperature stability of silicon nitride and silicon carbide

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