Late-phase melt conditions affecting the potential for in-vessel retention in high power reactors

Nuclear Engineering and Design

Volumn 230, Issue 1-3, 2004, Pages 133-150

  Knudson, D L ^a   Rempe, J L ^a   Condie, K G ^a   Suh, K Y ^b   Cheung, F B ^c   Kim, S B ^d  

^a IDAHO NATIONAL LABORATORY   (United States)

^b Seoul National University   (South Korea)

^c The Pennsylvania State University   (United States)

^d Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; COOLING; DEBRIS; HEAT FLUX; MELTING; MOLTEN MATERIALS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; RISK ASSESSMENT;

CORE MATERIALS; EXTERNAL REACTOR VESSEL COOLING (ERVC); HIGH POWER REACTORS; REACTOR DESIGNS;

NUCLEAR REACTORS;

EID: 2342463622     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.11.029     Document Type: Conference Paper

References (5)

1. © Code Manuals, INEEL/EXT-02/00589. Idaho National Engineering and Environmental Laboratory.
2. Rempe, J.L., Allison, C.M., 1995. Improved Models for Predicting Heat Transfer from a Molten Pool. Transactions from the 1995 ANS Winter Meeting, Thermal Hydraulics Division Proceedings, San Francisco, CA.
3. Rempe, J.L., et al., 1997. Potential for AP600 In-Vessel Retention through Ex-Vessel Flooding. Technical Evaluation Report, INEEL/EXT-97-00779. Idaho National Engineering and Environmental Laboratory.
4. Rempe, J.L., et al., 2004. Corium retention for high power reactors by an in-vessel core catcher in combination with external reactor vessel cooling, Nucl. Eng. Des. 230 (1-3), 293-309.
5. Stewart, W.A., et al., 1986. Experiments on natural circulation flows in steam generators during severe accidents. Proceedings of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San Diego, CA.