Study of the applicability of CFD calculation for HTTR reactor

Passive heat removal performance of the reactor vessel cavity cooling system (RCCS) is of primary concern for enhanced inherent safety of HTGR. In a loss of forced cooling accident, decay heat must be removed by radiation and natural convection of RCCS. Thus thermal hydraulic analysis of reactor int...

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Veröffentlicht in:	Nuclear engineering and design 2014-05, Vol.271, p.564-568
Hauptverfasser:	Tsuji, Nobumasa, Nakano, Masaaki, Takada, Eiji, Tokuhara, Kazumi, Ohashi, Kazutaka, Okamoto, Futoshi, Tazawa, Yujiro, Inaba, Yoshitomo, Tachibana, Yukio
Format:	Artikel
Sprache:	eng
Schlagworte:	Computational fluid dynamics Decay Fluid flow Hydraulics Nuclear engineering Nuclear power generation Nuclear reactor components Nuclear reactors
Online-Zugang:	Volltext
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