Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

Annals of Nuclear Energy

Volumn 33, Issue 11-12, 2006, Pages 945-956

  Yoo, Jaewoon ^a   Ishiwatari, Yuki ^a   Oka, Yoshiaki ^a   Liu, Jie ^a  

^a UNIVERSITY OF TOKYO   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; COUPLINGS; FAST REACTORS; NUCLEAR FUEL CLADDING; NUCLEAR FUELS; REACTOR CORES; STAINLESS STEEL;

FUEL ASSEMBLY; MIXED-OXIDE (MOX) FUELS; STAINLESS STEEL (SUS304); THERMAL HYDRAULIC COUPLING;

SUPERCRITICAL FLUIDS;

EID: 33747882212     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2006.07.004     Document Type: Article

References (10)

1. Burgreen D., et al. Vibration of rods induced by water in parallel flow. Trans. ASME 80 (1958) 991
2. Ishiwarari Y., et al. Safety of Super LWR (II) Safety Analysis at Supercritical Pressure. J. Nucl. Sci. Technol. 42 (2005) 935-948
3. Kitoh K., Koshizuka S., and Oka Y. Refinement of transient criteria and safety analysis for a high-temperature reactor cooled by supercritical water. Nucl. Technol. 135 (2001) 252-264
4. Mukohara T., Koshizuka S., and Oka Y. Core design of a high-temperature fast reactor cooled by supercritical light water. Ann. Nucl. Energ. 26 (1999) 1423-1436
5. Oka Y., and Jevremovic T. Negative coolant void reactivity in large fast breeder reactors with hydrogenous moderator layer. Ann. Nucl. Energ. 23 (1996) 1105-1115
6. Okumura, K., Kugo, T., Kaneko, K., Tsuchihashi, K., 2002. SRAC (Ver.2002); The Comprehensive Neutronics Calculation Code System. Department of Nuclear Energy System, Japan Atomic Energy Research Institute (JAERI).
7. Paidoussis M.P. An experimental study of vibration of flexible cylinders induced by nominally axial flow. Nucl. Sci. Eng. 35 (1969) 127-138
8. Suzuki, M., Saitou, H., 2004. Light Water Reactor Fuel Analysis Code FEMAXI-6 (Ver.1); Detailed Structure and User's Manual. Department of Reactor Safety Research, Nuclear Safety Research Center, Japan Atomic Energy Research Institute (JAERI).
9. Yamaji A., Oka Y., and Koshizuka S. Three-dimensional core design of high temperature supercritical-pressure light water reactor with neutronic and thermal-hydraulic coupling. J. Nucl. Sci. Technol. 42 (2005) 8-19
10. Yamaji A., Kamei K., Oka Y., and Koshizuka S. Improved core design of the high temperature supercritical-pressure light water reactor. Ann. Nucl. Energ. 32 (2005) 651-670