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

Fusion Engineering and Design

Volumn 49-50, Issue , 2000, Pages 703-707

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

^a EFREMOV INSTITUTE   (Russian Federation)

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

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; EXPERIMENTAL REACTORS; LITHIUM; STRESS ANALYSIS; THERMOANALYSIS;

LITHIUM COOLED FIRST WALL (FW); NEUTRONIC ANALYSIS; TEST BLANKET MODULE (TBM);

BREEDING BLANKETS;

EID: 0034315075     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(00)00175-7     Document Type: Article

References (8)

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7. T.Q. Hua Y. Gohar MHD pressure drops and thermal hydraulic analysis for the ITER breeding blanket design Fusion Eng. Des. Part A 27 1995 696 702
8. S. Molokov, Liquid metal flows in manifolds and expansions of insulating ducts in the plane perpendicular to a strong magnetic field, Report KfK, 5272, January 1994.