Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher-Reference-Cited by-同舟云学术

Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher

Published:2006-02 Issue:2 Volume:153 Page:208-223
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kang Kyoung-Ho¹,Park Rae-Joon¹,Kim Sang-Baik¹,Suh K.Y.²,Cheung F. B.³,Rempe J. L.⁴

Affiliation:

1. Korea Atomic Energy Research Institute, Thermal Hydraulic Safety Research Division Severe Accident Research Project, 150 Dukjin-dong,Yusong-gu, Daejeon 305-353, Korea

2. Seoul National University Seoul, Korea

3. The Pennsylvania State University University Park, Pennsylvania

4. Idaho National Engineering and Environmental Laboratory Idaho Falls, Idaho

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/NT06-A3701

Reference11 articles.

1. J. L. REMPE, S. A. CHAVEZ, G. L. ALLISON, G. E. KORTH, R. J. WITT, J. J. SIENICKI, S. K. WANG, L. A. STICKLER, C. H. HEATH, and S. D. SNOW, “Light Water Reactor Lower Head Failure Analysis,” NUREG/CR-5642, Idaho National Engineering Laboratory (1993).

2. T. G. THEOFANOUS, C. LIU, S. ADDITON, S. ANGELINI, O. KYMALAINEN, and T. SLAMASSI, “In-Vessel Coolability and Retention of a Core Melt,” DOE/ID-10640, Vol.1, U.S. Department of Energy (1995).

3. Conceptual design of an in-vessel core catcher

4. K. H. KANG, R. J. PARK, and S. B. KIM, “Synthetic Analyses of the LAVA Experimental Results on In-Vessel Corium Retention Through Gap Cooling,” KAERI/TR-1805/2001, Korea Atomic Energy Research Institute (2001).

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1. In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues;Nuclear Technology;2008-03

2. Simulant melt experiments on performance of the in-vessel core catcher;Nuclear Engineering and Design;2007-09

3. Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap;Nuclear Technology;2006-04