Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER-Reference-Cited by-同舟云学术

Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER

Published:2000-11 Issue: Volume:49-50 Page:703-707
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Vitkovsky I.V,Golovanov M.M,Divavin V.A,Kirillov I.R,Lipko A.V,Malkov A.A,Kartashev I.A,Komarov V.M,Ogorodnikov A.P,Schipakin O.L

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference8 articles.

1. J. Briesmeier, J. Hendrics, MCNP 4.2 Guide, LANL Report, Los Alamos National Laboratory, X-6 LANL, April 1991.

2. R.A. Forrest, J.-C. Sublet, FISPACT-3 User Manual, UKAEA Report, UKAEA FUS227, 1993.

3. Thermohydraulic optimization of liquid metal self-cooled breeding blankets;Kirillov;Fusion Technol.,1998

4. S.Y.Smolentsev, A.V.Tananaev, Development of computer code for analysis of heat transfer in liquid metal MHD flows in ducts, Second International Conference on Energy Transfer in MagnetoHydroDynamic Flows, Aussois, France, 1994, vol. 2, pp. 551–560.

5. Present understanding of MHD and heat transfer phenomena for liquid metal blankets;Kirillov;Fusion Eng. Des. Part A,1995

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