Title of article
Study of the applicability of CFD calculation for HTTR reactor
Author/Authors
Tsuji، نويسنده , , Nobumasa and Nakano، نويسنده , , Masaaki and Takada، نويسنده , , Eiji and Tokuhara، نويسنده , , Kazumi and Ohashi، نويسنده , , Kazutaka and Okamoto، نويسنده , , Futoshi and Tazawa، نويسنده , , Yujiro and Inaba، نويسنده , , Yoshitomo and Tachibana، نويسنده , , Yukio، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2014
Pages
5
From page
564
To page
568
Abstract
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 internals and RCCS is powerful means for evaluation of the heat removal performance of RCCS. The thermal hydraulic analyses using CFD computation tools are conducted for normal operation of the high temperature engineering test reactor (HTTR) and are compared to the temperature distribution of measured data. The calculated temperatures on outer faces of the permanent side reflector (PSR) blocks are in fair agreement with measured data. The transient analysis for decay heat removal mode in HTTR is also conducted.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2014
Journal title
Nuclear Engineering and Design Eslah
Record number
1594550
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