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Nuclear Technology Volume 98, 1992 - Issue 1
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Technical Paper

Study of Thermal-Hydraulic Characteristics during Decay Heat Removal in a Pool-Type Fast Breeder Reactor

Masayoshi AkutsuThe Japan Atomic Power Company 1-6-1 Ohte-machi, Chiyoda-ku, Tokyo 100, Japan
,
Yoshinobu OkabeThe Japan Atomic Power Company 1-6-1 Ohte-machi, Chiyoda-ku, Tokyo 100, Japan
,
Kazuziro SatohThe Japan Atomic Power Company 1-6-1 Ohte-machi, Chiyoda-ku, Tokyo 100, Japan
,
Hideki KamidePower Reactor and Nuclear Fuel Development Corporation O-arai Engineering Center, 4002 Narita-cho, O-arai-machi, Ibaraki 311-13, Japan
,
Kenji HayashiPower Reactor and Nuclear Fuel Development Corporation O-arai Engineering Center, 4002 Narita-cho, O-arai-machi, Ibaraki 311-13, Japan
,
Nobuyuki NaoharaCentral Research Institute of Electric Power Industry 2-11-1 Iwatokita, Komae-shi, Tokyo 201, Japan
,
Kengo IwashigeHitachi, Ltd., Energy Research Laboratory 1168 Moriyama-cho, Hitachi-shi 316, Japan
&
Yoji ShibataHitachi, Ltd., Hitachi Works, 3-1-1 Saiwai-cho Hitachi-shi 317, Japan
 show all
Pages 14-26 | Published online: 13 May 2017

References

  • T. BEAVER and H. JOHNSON, “Transient Testing of the FFTF for Decay Heat Removal by Natural Convection,” Proc. Int. Topl. Mtg. Liquid Metal Fast Breeder Reactor Safety and Related Design and Operational Aspects, Lyons, France, July 19-23, 1982, p. II-525.
  • T. SUZUKI, Y. NAGAOKA, K. HIRAO, H. TANIYAMA, Y. MATSUNO, Z. OGISO, N. HANDA, K. OGURA, and H. KAJIWARA, “Natural Circulation Test in Experimental Fast Reactor ’JOYO’,” J. At. Energy Soc. Jpn., 25, 9, 729 (1983).
  • H. PLANCHON, R. SINGER, D. MOHRM, and E. FELDMAN, “The Experimental Breeder Reactor II Inherent and Heat Removal Tests-Results and Analysis,” Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21-25, 1985, Vol. 1, p. 281, American Nuclear Society (1985).
  • G. PERTMER, H. HOFFMANN, and D. WEINBERG, “2D and 3D Model Experiments for the SNR-2 DHR by Natural Convection,” Proc. 2nd Thermal Engineering Conf., Honolulu, Hawaii, March 22-27, 1987.
  • H. HOFFMANN, D. WEINBERG, and Y. IEDA, “Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors,” Nucl. Technol., 88, 75 (1989).
  • D. WEINBERG, K. MARTEN, Y. IEDA, H. HOFFMANN, and H. FREY, “Investigation into LMFBR Decay Heat Removal by Natural Convection Under Nominal and Non-Nominal Conditions,” Proc. American Society of Mechanical Engineers Annual Mtg., Chicago, Illinois, November 28-December 2, 1988.
  • C. ESSIG, B. BERTHET, E. MANCUSO, E. GESI, A. GOURIOU, P. BERGEONNEAU, V. ERTEL, A. REETZ, and A. DONATI, “Dynamic Behaviour of RAP-SODIE in Exceptional Transient Experiments,” Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21-25, 1985, Vol. 1, p. 635, American Nuclear Society (1985).
  • I. MAEKAWA and Y. IEDA, “Current Status on Thermal Stratification Study,” Proc. 4th Int. Conf. Liquid Metal Engineering and Technology, Avignon, France, October 17-21, 1988, p. 404-1.
  • M. OHTSUKA and M. YAMAKAWA, “Thermal Hydraulic Analysis in LMFBR Plenum,” Proc. Int. Conf. Numerical Methods in Nuclear Engineering, Montreal, Canada, September 6-9, 1983.
  • S. GREWAL and E. GLUEKLER, “Water Simulation of Sodium Reactors,” Chem. Eng. Commun., 17, 343 (1982).

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