Safety analysis of small long life CANDLE fast reactor

Annals of Nuclear Energy

Volumn 35, Issue 5, 2008, Pages 813-828

  Yan, Mingyu ^a   Sekimoto, Hiroshi ^a  

^a TOKYO INSTITUTE OF TECHNOLOGY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; COMPUTER SIMULATION; COOLANTS; HEAT LOSSES; LEAD COMPOUNDS; URANIUM COMPOUNDS;

SAFETY ANALYSIS; STATIONARY DIFFUSION CALCULATION; STEADY STATE; THERMAL HYDRAULIC CALCULATION;

FAST REACTORS;

EID: 41749118188     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.09.009     Document Type: Article

References (15)

1. Cheng S.K., and Todreas N.E. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles. Nucl. Eng. Des. 92 (1986) 227
2. Davis C.B., and Kim D. Core power limits for a lead-bismuth natural circulation actinide burner reactor. Nucl. Eng. Des. 213 (2002) 165-182
3. Handa M., Fukushima S., and lwai T. The characteristics and irradiation behaviours of U-Pu mixed oxide, carbide, nitride and metal fuels for FBRs. J. Atomic Energy Soc. Jpn. (AESJ) 31 (1989) 886-893
4. Hayes S.L., Thomas J.K., and Peddicord K.L. Material property correlations for uranium mononitride. J. Nucl. Mater. 171 (1990) 300-318
5. Hiraoka T., et al. A high-breeding fast reactor with fission product gas purge/tube-in-shell metallic fuel assemblies. Nucl. Technol. 93 (1991) 305
6. Kakac S., Shah R.K., and Aung W. Handbook of Single-Phase Convective Heat Transfer (1987), Wiley pp. 7.1-7.62
7. Kato T., et al. The utilization handbook of the recommended data of decay heat. JAEA (1990) 24-27
8. Okumura, K., Kaneko, K., Tsuchihashi, K., 1996. SRAC95: general purpose neutronics code system. JAERI-Data/Code 96-015. Japan Atomic Energy Research Institute, Japan.
9. Raznjevic K. Handbook of Thermodynamic Tables and Charts (1976), Hemisphere, Washington, DC
10. Sekimoto H., and Udagawa Y. Effects of fuel and coolant temperatures and neutron fluence on CANDLE burnup calculation. J. Nucl. Sci. Technol. 43 2 (2006) 189-197
11. Sekimoto H., and Zaki S. Design study of lead- and lead-bismuth-cooled small long-life nuclear power reactors using metallic and nitride fuel. Nucl. Technol. 109 3 (1994) 307-313
12. Shure, K, WAPD-BT-24, 1961.
13. Tong L.S., and Weisman J. Thermal Analysis of Pressurized Water Reactors (1979), American Nuclear Society
14. Waltar A.E., and Reynolds A.B. Fast Breeder Reactors (1981), Pergamon, New York
15. Yan, M.Y., Sekimoto, H., in press. Design research of small long life CANDLE fast reactor, Annals of Nuclear Energy.