Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

Nuclear Technology

Volumn 152, Issue 2, 2005, Pages 162-169

  Jeong, Yong Hoon ^a   Chang, Soon Heung ^a   Baek, Won Pil ^b  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

^b Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Critical heat flux; In vessel retention; Severe accident

Indexed keywords

CHANNEL FLOW; COMPOSITION EFFECTS; COMPUTER SIMULATION; CONTAINMENT VESSELS; COOLING; HEAT FLUX; MASS TRANSFER; NUCLEAR REACTOR ACCIDENTS; SODIUM COMPOUNDS; THERMAL VARIABLES MEASUREMENT; WALL FLOW; WATER;

CRITICAL HEAT FLUX (CHF); IN-VESSEL RETENTION; MASS FLUX; NUCLEAR REACTOR DESIGN; REACTOR VESSEL; SEVER ACCIDENT; SUBCOOLING; TRISODIUM PHOSPHATE;

NUCLEAR REACTORS;

EID: 27144477694     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT05-A3667     Document Type: Article

References (7)

1. T. G. THEOFANOUS, C. LIU, S. ADDITON, S. ANGELINI, O. KYMÄLÄNEN, and T. SALMASSI, "In-Vessel Coolability and Retention of a Core Melt," Nucl. Eng. Des, 169, 1 (1997).
2. T.G. THEOFANOUS and S. SYRI, "The Coolability Limits of a Reactor Pressure Vessel Lower Head," Nucl. Eng. Des., 169, 59 (1997).
3. T.-N. DINH, J. P. TU, T. SALMASSI, and T. G. THEOFANOUS, "Limits of Coolability in the AP1000-Related ULPU-2400 Configuration V Facility," CRSS-03/06, Center for Risk Studies and Safety, University of California, Santa Barbara (2003).
4. J. M. BONNET, S. ROUGE, and J. M. SEILER, "Large Scale Experiments for Core Melt Retention-BALI: Corium Pool Thermal Hydraulics SULTAN: Boiling Under Natural Convection," Proc. OECD/NEA Workshop on Large Molten Pool Heat Transfer, Nuclear Research Centre, Grenoble, France, March 9-11, 1994 (1994).
5. S. ROUGE, "SULTAN Test Facility Large Scale Vessel Coolability in Natural Convection at Low Pressure," Proc. NURETH-7, Saratoga Springs, New York, September 10-15, 1995, p. 1949 (1995).
6. M. CAIRA, G. CARUSO, A. NAVIGLIO, and S. ROUGE, "CHF Prediction for Sloping Surfaces," Proc. 5th Int. Topl. Mtg. Nuclear Thermal Hydraulic Operation and Safety (NUTHOS-5), Beijing, China, April 14-18, 1997, p, AA7-1 (1997).
7. F. B. CHEUNG and K. H. HADDAD, "A Hydrodynamic Critical Heat Flux Model for Saturated Pool Boiling on a Downward Facing Curved Heating Surface," Int. J. Heat Mass Transfer, 40, 6, 1291 (1997).