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Volumn 81 A, Issue 1-4, 2006, Pages 695-700

Design approach for the main ITER test blanket modules for the EU helium cooled lithium-lead blankets

Author keywords

HCLL; Test blanket module design

Indexed keywords

EXPERIMENTAL REACTORS; HELIUM; INSTRUMENT COMPONENTS; LITHIUM ALLOYS; OPTIMIZATION;

EID: 31744439811     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.08.054     Document Type: Conference Paper
Times cited : (11)

References (6)
  • 2
    • 31744447662 scopus 로고    scopus 로고
    • Helium cooled lithium lead test blanket module for ITER - Status of the design, analyses and test programme in ITER
    • DM2S/SERMA, October
    • A. Li Puma, L. Giancarli, Y. Poitevin, G. Rampal, J. Szczepanski, Helium cooled lithium lead test blanket module for ITER - status of the design, analyses and test programme in ITER, CEA Report, DM2S/SERMA, October 2004.
    • (2004) CEA Report
    • Li Puma, A.1    Giancarli, L.2    Poitevin, Y.3    Rampal, G.4    Szczepanski, J.5
  • 5
    • 31744442627 scopus 로고    scopus 로고
    • Preliminary feasibility study of the manufacturing technologies and the assembly procedures of the ITER test blanket modules
    • December
    • C. Boudot, C. Dippold, N. Everott, Preliminary feasibility study of the manufacturing technologies and the assembly procedures of the ITER test blanket modules, EFET Report n°EFDA 93/851IR, December 2004.
    • (2004) EFET Report N°EFDA 93/851IR , vol.EFDA 93-851IR
    • Boudot, C.1    Dippold, C.2    Everott, N.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.