Fast Reactors and Accelerator Driven Systems Knowledge Base
IAEA-TECDOC--1348: Power Reactor and Sub-critical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material
Advisory Group Meeting on “Design and Performance of Reactor and Sub-critical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material” , Moscow, Russian Federation, 23-27 October 2000
International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--1348
Abstract
The Advisory Group Meeting (AGM) on “Design and Performance of Reactor and Sub-critical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material” was held in Moscow, Russian Federation from 23-27 October 2000. This AGM was convened by the International Atomic Energy Agency (IAEA) and was hosted by the Research and Development Institute of Power Engineering (RDIPE) in Moscow, in cooperation with the Institute of Physics and Power Engineering (IPPE) in Obninsk, and Minatom. Its purpose was to provide a forum for international information exchange on all the topics relevant to lead (Pb) and lead-bismuth (Pb-Bi) cooled critical and sub-critical reactors. In addition, the AGM aimed at: (1) finding ways and means to improve international co-operation efforts in this area; (2) obtaining advice from the Member States with regard to the activities to be implemented in this area by the IAEA, in order to best meet their needs; and (3) laying out the plans for an effective co-ordination and support of the R&D activities in this area.
view the full text of this conference report (format: PDF, size= 2740kB, 236 pages)
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- covers (2 pages, format: PDF, size= 84kB )
- foreword (2 pages, format: PDF, size= 115kB )
- contents (2 pages, format: PDF, size= 114kB )
- summary (6 pages, format: PDF, size= 147kB )
- list of participants (2 pages, format: PDF, size= 82kB )
Articles
Nuclear power strategy: Requirements for technology
V.V. Orlov, V.I. Rachkov
Nuclear power of the coming century and requirements to the nuclear technology
V.V. Orlov, V. Leonov, A.G. Sila-Novitski, V. Smirnov, V. Tsikunov, A.I. Filin
Evolution of the technical concepts of fast reactors: The concept of BREST
V.V. Orlov
Design features of BREST reactors and experimental work to advance the concept of BREST reactors
A.I. Filin, V.V. Orlov, V.N. Leonov, A.G. Sila-Novitski, V.S. Smirnov,
V.S. Tsikunov
Current status and plans for development of NPP with BREST reactors
A.I. Filin
Experimental studies of BREST-OD-300 reactor characteristics on BFS facilities
I.P. Matveenko, A.M. Tsyboulia, G.N. Manturov, M.Y. Semyonov,
V.N. Kocsheyev, V.S. Smirnov, A.V. Lopatkin, V.G. Muratov, P.N. Alexeyev
Mononitride U-Pu mixed fuel and its electrochemical reprocessing in molten salts
B.D. Rogozkin, N.V. Stepennova, Yu.E. Fedorov, O.N. Dubrovin,
M.G. Shishkov, O.A. Alekseev, T.D. Loushnikova, S.I. Balakireva, V.V. Shentiakov
The BOR-60 loop-channel design for testing the BREST reactor fuel
V.N. Efimov, I.Yu. Zhemkov, N. Kozolup, V.I. Polyakov, V.T. Stepanov,
Yu.E. Stynda, V.V. Orlov, A.I. Filin, A.G. Sila-Novitski, A.A. Pikalov
Lead coolant as a natural safety component
V.V. Orlov, V.N. Lenov, A.G. Sila-Novitski, V.S. Smirnov, A.I. Filin, V.S. Tsikunov
Issues of lead coolant technology
Yu.I. Orlov, P.N. Martynov, V.A. Gulevsky
Experimental and computational study on core thermohydraulics of BREST-type
reactors (lead cooling)
A.D. Efanov, A.V. Zhukov, Ju.A. Kuzina, A.P. Sorokin, V.P. Smirnov,
A.G. Sila-Novitski
Corrosion resistance of structure materials in lead coolant with reference to reactor
installation BREST-OD-300
A. Roussanov, V. Troyanov, G. Jachmenev, A. Demishonkov
Multipurposed small fast reactor SVBR-75/100 cooled by plumbum-bismuth
A.V. Zrodnikov, V.I. Chitaykin, B.F. Gromov, O.G. Grigoriev, A.V. Dedoul,
G.I. Toshinsky, Yu.G. Dragunov, V.S. Stepanov
Conceptual design studies on various types of HLMC fast reactor plants
T. Mihara, Y. Tanaka, Y. Enuma
Status report on the ADS research activity in Italy
S. Buono, C. Aragonese, L. Maciocco, V. Moreau, L. Sorrentino
The INP (Kazakhstan) activity in the field of accelerator-driven subcritical systems
O.P. Maksimkin, S.V. Zhdanov
MYRRHA: A multipurpose accelerator driven system for research & development
Ph. Benoit, H. Aït Abderrahim, P. Kupschus, E. Malambu, K. Van Tichelen,
B. Arien, F. Vermeersch, V. Jongen, S. Ternier, D. Vandeplassche
Design of a molten heavy-metal coolant and target for fast-thermal accelerator driven
sub-critical system (ADS)
B. Satyamurthy, S.B. Deqwekar, P.K. Nema
Design progress of HYPER system
W.S. Park, W. Hwang, Y.H. Kim, N.I. Tak, T.Y. Song
Study on ADS Pb (Pb-Bi) spallation target
Z. Zhao, Z. Luo, Y. Xu, D. Ding
