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Volumn , Issue , 2003, Pages 491-500

Neutronic characterisation of the high flux test module of the international fusion material irradiation facility

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; FUSION REACTIONS; FUSION REACTORS; IRRADIATION; LITHIUM; MONTE CARLO METHODS; NEUTRONS; OPTIMIZATION; RADIATION DAMAGE;

EID: 2642516525     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (4)

References (19)
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  • 4
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  • 5
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    • Development of methods for calculation of n+Li and d+Li cross sections for energies up to 50 MeV
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  • 6
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    • Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data
    • S.P. SIMAKOV, U. FISCHER, U. VON MÖLLENDORFF et al., "Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data," Journ. Nucl. Mat., 307-311, 1710 (2002).
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  • 7
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    • International fusion material irradiation facility (IFMIf): Neutron source term simulation and neutronics analyses of the high flux test module
    • Forschungszentrum Karlsruhe, Karlsruhe, Germany
    • S.P. SIMAKOV, U. FISCHER, V. HEINZEL et al., "International Fusion Material Irradiation Facility (IFMIF): Neutron Source Term Simulation and Neutronics Analyses of the High Flux Test Module," FZKA-6743, Forschungszentrum Karlsruhe, Karlsruhe, Germany (2002).
    • (2002) FZKA-6743
    • Simakov, S.P.1    Fischer, U.2    Heinzel, V.3
  • 8
    • 0036901569 scopus 로고    scopus 로고
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    • U. FISCHER, S.P. SIMAKOV, A.YU. KONOBEEV et al., "Neutronics and Nuclear Data for the IFMIF neutron source," Fus. Eng. Des., 63-64, 493 (2002).
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  • 9
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  • 11
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    • M.B. CHADWICK, P.G. YOUNG et al., "Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX," Nucl. Sci. Eng., 131, 293 (1999).
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.