著者

Fumizawa Motoo

出版者

湘南工科大学

雑誌

湘南工科大学紀要 (ISSN:09192549)

巻号頁・発行日

vol.41, no.1, pp.1-8, 2007-03-18

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This study presents an experimental method of porosity evaluation and a predictive thermal-hydraulic analysis withpacked spheres in a nuclear reactor core. The porosity experiments were carried out in both a fully shaken state with theclosest possible packing and in a state of non-vibration. The predictive analysis considering the fixed porosity value wasapplied as a design condition for an Ultra High Temperature Reactor Experiment (UHTREX). The thermal-hydrauliccomputer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316°C wasachieved in the case of an UHTREX at Los Alamos Scientific Laboratory, which was a small scale UHTR. In the presentstudy, the fuel was changed to a pebble type, a porous media. In order to compare the present pebble bed reactor andUHTREX, a calculation based on HTGR-GT300 was carried out in similar conditions with UHTREX; in other words,with an inlet coolant temperature of 871°C, system pressure of 3.45MPa and power density of 1.3 W/cm3. As a result, thefuel temperature in the present pebble bed reactor showed an extremely lower value compared to that of UHTREX.