The next generation of fast reactors

Nuclear Engineering and Design

Volumn 173, Issue 1-3, 1997, Pages 143-150

  Adamov, E ^a   Orlov, V ^a   Filin, A ^a   Leonov, V ^a   Sila Novitski, A ^a   Smirnov, V ^a   Tsikunov, V ^a  

^a DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING NIKIET   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0000396671     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(97)00098-8     Document Type: Article

References (5)

1. Adamov, E.O., Orlov, V.V., Filin et al., 1994. Conceptual design of BREST-300 lead-cooled fast reactor, Proc. Int. Topical Meet, on Advanced Reactors Safety, ARS'94, Pittsburgh, USA, pp. 509-516.
2. Alexeev, P.N., Levin, B.E., Morozov, A.G., Orlov, V.V., Slesarev, I.S., Subbotin, S.A., 1989. Conception of safe reactor RB-EC. Kurchatov Institute Report, No. 35/1-322-88, Moscow, (in Russian).
3. Orlov, V.V., 1987. Nuclear breeding and reactor safety. Proc. World Sci. Forum on Power in XXI Century, IVTAN, Moscow, (in Russian).
4. Orlov, V.V., Avrorin, E.N., Adamov, E.O., et al., 1992. Non-traditional conceptions of NPP with natural safety. Atom. Energ. 72, 317-328.
5. Orlov, V.V, et al., 1994. Study of ultimate accidents for lead-cooled fast reactor. Proc. Int. Topical Meet, on Advance Reactor Safety, ARS'94, Pittsburgh, USA, pp. 538-544.