Conceptual and safety design of Pb-Bi cooled direct contact boiling water fast reactor (PBWFR)

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 2, Issue , 2005, Pages 848-856

  Uchida, S ^a   Takahashi, M ^b   Koyama, K ^a   Yamada, Y ^a  

^a Advanced Reactor Technology Co Ltd   (Japan)

^b TOKYO INSTITUTE OF TECHNOLOGY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; COOLING; COOLING SYSTEMS; FAST REACTORS; HEAT EXCHANGERS; LEAD METALLURGY; SAFETY ENGINEERING; STEAM GENERATORS;

CIRCULATION PUMPS; UPPER PLENUM;

BOILING WATER REACTORS;

EID: 34249044785     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. J.Buongiomo, N.E.Todreas, et al. "Key Features of an Integrated Pb-Bi Cooled Reactor Based on Water/Liquid-Metal Direct Heat Transfer", Trans. Of The 1999 ANS Winter, Meeting, Long Beach (U.S.A.), November 1999.
2. J.Buongiomo, N.E.Todreas, et al. "Conceptual Design of a Lead-Bismuth Cooled Fast Rector with In-Vessel Direct-Contact Steam Generation", MIT-ANP-TR-079, Center for Advanced Nuclear Energy Systems Massachusetts Institute o Technology, (March 2001).
3. Grachev N.S., Drobyshev N.V., Kirillov P.L. "Mixing steam generators with liquid metal, Proc. Intern. Conf. on Liquid Metals", March 16-18, 1993, Karlsruhe, Germany.
4. Grachev N.S., Kirillov P.L., Martynov P.N., "Steam generators With direct contact between lipuid metals and water", Proc. NURETH-9, Oct. 3-8, 1999, San Francisco, USA, (CD).