Current design status of sodium cooled super-safe, small and simple reactor

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 2, Issue , 2002, Pages 733-739

  Ueda, N ^a   Kinoshita, I ^a   Nishi, Y ^a   Minato, A ^a   Yokoyama, T ^a   Nishiguchi, Y ^a  

^a CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BURNUP SWING; SMEAR DENSITY; UNPROTECTED LOSS OF FLOW;

COOLANTS; DENSITY OF LIQUIDS; FLOW OF FLUIDS; HEAT EXCHANGERS; NUCLEAR FUEL CLADDING; PRESSURE DROP; REACTIVITY (NUCLEAR); SODIUM; STEAM GENERATORS; TEMPERATURE MEASUREMENT;

REACTOR CORES;

EID: 0036393422     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE10-22353     Document Type: Conference Paper

References (6)

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2. Hattori, S., Minato, A., 1995, "A Large Modular LMR Power Station which Meets Current Requirements", Procedure of the 3rd ASME-JSME International Conference on Nuclear Engineering (ICONE-3), S207-4, Kyoto, Apr. 23-27.
3. Nakamura, K., Ogata, T., Kurata, M., Yokoo, T., Mignanelli, A., 2001, "Reactions of Urnanium-Pltonium Alloys with Iron", AESJ Journal of Nuclear Science and Technology, 38,-2, pp. 112-119.
4. Ogata, T., Yokoo, 1999, "Development and Validation of ALFUS: an Irradiation Behavior Analysis Code for U-Pu-Zr Ternary Alloy Fuels", Nuclear Technology, 128, pp. 113-123.
5. Ueda, N., Kinoshita, I., Nishi, Y., Minato, A., Matshumiya M., and Nishiguchi, Y., 2002, "Passive Safety Features in Sodium Cooled Super-Safe, Small and Simple Reactor", Procedure of the 10th ASME-JSME International Conference on Nuclear Engineering (ICONE-10)
6. Yokoyama, T., Ueda, N., 1994, "Reactivity Evaluation of Fast Reactor Core Controlled by Azimuth Separated Reflector at Withstand Accident", Procedure of the 3rd ASME-JSME International Conference on Nuclear Engineering (ICONE-3), S209-3, Kyoto, Apr. 23-27.