Fuel cycle design evolution from FDR-ITER to RTO/RC-ITER

Fusion Engineering and Design

Volumn 49-50, Issue , 2000, Pages 893-898

  Murdoch, D K ^a   Glugla, M ^b   Kveton, O ^c  

^a MAX PLANCK INSTITUT FÜR PLASMAPHYSIK   (Germany)

^b KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^c ITER Canada   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

NUCLEAR FUELS; NUCLEAR POWER PLANTS; PLASMA APPLICATIONS; TRITIUM;

FUEL CYCLE;

EXPERIMENTAL REACTORS;

EID: 0034314897     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(00)00328-8     Document Type: Article

References (10)

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6. S.K. Sood, O.K. Kveton et al., Tritium Systems Concepts for the Next European Torus (NET), CFFTP-G-86020, September 1986.
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8. J.R. Robins et al., Tritium Purification System for TFTR, Proc. 15th IEEE/NPSS Symposium Fusion Engineering, Volume One, October 11-15, 1993.
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