THERMAL EVALUATION FOR A ULTRA HIGH TEMPERATURE REACTOR WITH PEBBLE TYPE FUELS

被引：0

作者：

Fumizawa, Motoo ^{[1
]}

Kosuge, Yuta ^{[1
]}

Hortuchi, Hidenori ^{[1
]}

机构：

[1] SIT, MSE Dept, Fujisawa, Kanagawa 2518511, Japan

来源：

ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1 | 2009年

关键词：

D O I：

暂无

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 was achieved in the case of an UHTREX at LASL. which was a small scale UHTR using hollow-rod as a fuel element In the present study, the fuel was changed to a pebble type, a porous media Several calculation based on HTGR-GT300 through GT600 were 4 8 w/cm(3) through 9 6 w/cm(3) respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected

引用

页码：865 / 872

页数：8

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