Safety analysis of reactivity initiated accidents in a HPLWR reactor by the coupled ATHLET-KIKO3D code

Progress in Nuclear Energy

Volumn 52, Issue 2, 2010, Pages 190-196

  Maraczy Cs ^a   Kereszturi A ^a   Trosztel, I ^a   Hegyi, Gy ^a  

^a KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

Author keywords

High Performance Light Water Reactor; Reactivity Initiated Accident (RIA); Supercritical coolant

Indexed keywords

ACCEPTANCE CRITERIA; CHANNEL TEMPERATURE; DYNAMIC CORES; HEAT TRANSFER CORRELATION; HIGH-PERFORMANCE LIGHT WATER REACTORS; NEUTRONICS; POWER DISTRIBUTIONS; POWER INCREASE; POWER PEAKING FACTOR; REACTIVITY INITIATED ACCIDENT; REACTIVITY INITIATED ACCIDENT (RIA); REACTOR POWER; SAFETY ANALYSIS; SINGLE CHANNELS; SUPER-CRITICAL; SUPERCRITICAL WATER; SUPERCRITICAL WATER COOLED REACTORS; THERMAL HYDRAULICS;

ACCIDENTS; COOLANTS; ESTUARIES; HYDRAULICS; LIGHT WATER REACTORS; MODERATORS; PRESSURIZED WATER REACTORS;

COUPLED CIRCUITS;

EID: 70450221938     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2009.06.005     Document Type: Article

References (8)

1. Burwell M.J. The Thermalhydraulic Code ATHLET for Analysis of PWR and BWR Systems (1989), NURETH-4, Karlsruhe, Germany pp. 10-13 October
2. Ishiwatari, Y., Oka, Y., Koshizuka, S., Liu, J., 2007. Safety characteristics of the super LWR design concept. In: Proceedings of ICAPP 2007, Paper 7309, Nice, France, 13-18 May.
3. Jackson J.D., and Hall W.B. Forced convection heat transfer to fluids at supercritical pressure. In: Kakac S., and Spalding D.B. (Eds). Turbulent Forced Convection in Channels and Bundles vo1. 2 (1979), Hemisphere Pub. 563
4. Keresztúri A., Hegyi Gy., Maráczy Cs., Panka I., Telbisz M., Trosztel I., and Hegedüs C. Development and validation of the three-dimensional dynamic code - KIKO3D. Annals of Nuclear Energy 30 (2003) 93-120
5. Kirillov, P., Pometko, R., Smirnov, A., Grabezhnaia, V., Pioro, I., Duffey, R., Khartabil, H., 2005. Experimental study on heat transfer to supercritical water flowing in 1- and 4-m-long vertical tubes. In: Proceedings of GLOBAL 2005, Paper No. 518, Tuskuba, Japan, 9-13 October.
6. Pismenny, E., Razumovskiy, V., Maevskiy, E., Koloskov, A., Pioro, I., Duffey, R., 2005. Experimental study on temperature regimes to supercritical water flowing in vertical tubes at significant impact of free convection. In: Proceedings of GLOBAL 2005, Paper No. 519, Tuskuba, Japan, 9-13 October.
7. Schulenberg, T., 2006. Core and fuel assembly design options for a thermal SCWR. Workshop on fuelled loop tests for SCWR R&D, Paris, France, 20 March.
8. Yamaji, A., Tanabe, T., Oka, Y., Yang, J., Liu, J., Ishiwatari, Y., Koshizuka, S., 2005. Evaluation of the nominal peak cladding surface temperature of the super LWR with subchannel analyses. In: Proceedings of GLOBAL 2005, Paper No. 557, Tsukuba, Japan, 9-13 October.