Core design feature studies and research needs for high performance light water reactors

2003 International Congress on Advances in Nuclear Power Plants - Proceedings of ICAPP 2003

Volumn , Issue , 2003, Pages

  Rimpault, G ^a   Maraczy C ^b   Kyrki Rajamaki R ^c   Oka, Y ^d   Schulenberg, T ^e  

^a IRFM   (France)

^b WIGNER RESEARCH CENTRE FOR PHYSICS   (Hungary)

^c VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

^d UNIVERSITY OF TOKYO   (Japan)

^e KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; COOLANTS; CURRICULA; FLOW OF WATER; HYDRAULICS; LIGHT WATER REACTORS; METAL CLADDING; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS; STEAM TURBINES; THERMAL INSULATION; WATER ABSORPTION;

ADVANCED DESIGNS; APPROPRIATE DESIGNS; CLADDING MATERIAL; COOLANT TEMPERATURE; EUROPEAN COMMUNITY; HIGH-PERFORMANCE LIGHT WATER REACTORS; REFERENCE CONCEPTS; REFERENCE DESIGNS;

STRUCTURAL DESIGN;

EID: 84933180884     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. Dobashi, K, Oka, Y, Koshizuka, S.: Conceptual Design of a High Temperature Power Reactor Cooled and Moderated by Supercritical Light Water, Ann. Nucl. Energy, Vol. 25, pp. 487-505 (1998)
2. Okano, Y, Koshizuka, S. and Oka, Y: Design of Water Rod Cores of a Direct-cycle Supercritical-pressure Light Water Reactor, Ann. Nucl. Energy, Vol. 21, pp. 601-611, (1994)
3. Cs. Hegedüs, Gy Hegyi, G. Hordósy, A. Keresztúri, M. Makai, Cs. Maráczy, F Telbisz, E. Temesvári, P. Vértes: The KARATE Program System, Physor 2002, Seoul, Korea, October 7-10, 2002
4. Rimpault G. et al; The ERANOS Code and Data System for Reactor Neutronic Analyses, Physor 2002, Seoul, KOREA, October 7-10 2002
5. Briesmeister, J. (ed.) MCNP - A General Monte Carlo N-Particle Transport Code, Version 4B. LANL-12625-M. 1997.
6. P. Morris, D.K. Ross, A. Ivanov, D.R. Weaver, O. Serot, Inelastic Neutron Scattering Study of the Vibration Frequencies of Hydrogen in Calcium Dihydride, MH'2002, 2nd to 6th September 2002, Annecy, France
7. Toumi, I., Gallo D. and Royer E. Advanced Numerical Methods for three dimensional Two-Phase Flow Calculations in PWR, NURETH-8 Eight International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Kyoto, Japan, Sept. 30 - Oct. 4, 1997
8. Cheng, X., Schulenberg, T., Koshizuka, S., Oka, Y., Souyri, A., 2002. Thermal-Hydraulic Analysis of Supercritical Pressure Light Water Reactors, Proc. of Int. Congress on Advanced Nuclear Power Plants, June 9-13, 2002, Hollywood, Florida. USA
9. Williams T., Chawla R., Grimm P., Joneja O.P., Seijer R. Ziver A. K.; LWR-PROTEUS New Experiments at a Zero-Power Facility Using Power Reactor Fuel, Proc. Int. Conf. on the Physics of Nuclear Science and Technology, Long Island, October 5-8, 1998
10. Yamamoto T., Iwata, Y. and Ueji M. NUPEC, Cathalau S., Fougeras P., Chauvin J.P. and Blaise P., Santamarina A.CEA, BASALA: Advanced BWR MOX Core Physics Experiments, Physor2000 ANS Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the next Millennium Pittsburgh USA 7-11 May 2000
11. Koshizuka, S. and Oka, Y.: Computational Analysis of Deterioration Phenomena and Thermal Hydraulic Design of SCR, Proc. SCR2000 Symposium, November 6-9, 2000 Tokyo, The University of Tokyo, Japan(2000).
12. Kitoh, K., Koshizuka, S. and Oka, Y.: Refinement of Transient Criteria and Safety Analysis of a High Temperature Reactor Cooled by Supercritical Water, Proc. ICONE-7, ICONE-7234, ASME, 1999
13. Cheng, X., Schulenberg, T., Bittermann, D., Design Analysis of Core Assemblies for Supercritical Steam Conditions, submitted for publication to Nuclear Engineering and Design, 2002.