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Volumn 2008, Issue , 2008, Pages

Fission product transport and source terms in HTRs: Experience from AVR pebble bed reactor

Author keywords

[No Author keywords available]

Indexed keywords

DEPOSITION BEHAVIOR; DESIGN BASIS ACCIDENTS; DUST CONCENTRATIONS; FLOW PERTURBATIONS; NORMAL OPERATIONS; SORPTION CAPABILITY; SOURCE TERM ESTIMATION; TRANSPORT BEHAVIOR;

EID: 64249098805     PISSN: 16876075     EISSN: 16876083     Source Type: Journal    
DOI: 10.1155/2008/597491     Document Type: Article
Times cited : (80)

References (37)
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  • 11
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    • (1991) Nuclear Technology , vol.94 , pp. 56-67
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    • 0035448103 scopus 로고    scopus 로고
    • Source term estimation for small-sized HTRs: Status and further needs, extracted from German safety analyses
    • Moormann R., Schenk W., Verfondern K., Source term estimation for small-sized HTRs: status and further needs, extracted from German safety analyses. Nuclear Technology 2001 135 3 183 193 (Pubitemid 32829080)
    • (2001) Nuclear Technology , vol.135 , Issue.3 , pp. 183-193
    • Moormann, R.1    Schenk, W.2    Verfondern, K.3
  • 19
    • 84887008557 scopus 로고    scopus 로고
    • Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors (IWGGCR-13) October 1985 Berkeley, UK
    • Röllig K., Christ A., Haase F. W., Wiedmann J., Caesium deposition on HTR primary circuit materials. Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors (IWGGCR-13) October 1985 Berkeley, UK 329 350
    • Caesium Deposition on HTR Primary Circuit Materials , pp. 329-350
    • Röllig, K.1    Christ, A.2    Haase, F.W.3    Wiedmann, J.4
  • 25
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    • Staub im AVR-Reaktor, eine Analyse der Kaltgasfilterversuche
    • May 1987 Karlsruhe, Germany
    • Wawrzik U., Staub im AVR-Reaktor, eine Analyse der Kaltgasfilterversuche. Proceedings of the Jahrestagung Kerntechnik May 1987 Karlsruhe, Germany 315 318
    • Proceedings of the Jahrestagung Kerntechnik , pp. 315-318
    • Wawrzik, U.1
  • 28
    • 0742268394 scopus 로고    scopus 로고
    • Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite
    • 10.1016/j.nucengdes.2003.11.001
    • Moormann R., r.moormann@fz-juelich.de Hinssen H.-K., Kühn K., Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite. Nuclear Engineering and Design 2004 227 3 281 284 10.1016/j.nucengdes.2003.11.001
    • (2004) Nuclear Engineering and Design , vol.227 , Issue.3 , pp. 281-284
    • Moormann, R.1    Hinssen, H.-K.2    Kühn, K.3
  • 31
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    • Results of AVR-experiments
    • Dusseldorf, Germany VDI
    • Kirch N., Ivens G., Results of AVR-experiments. AVR-Experimental HTR 1990 Dusseldorf, Germany VDI
    • (1990) AVR - Experimental HTR
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  • 33
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    • Results of experiments at the AVR reactor
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    • Gottaut, H.1    Krüger, K.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.