Design Study of 400mwt High Temperature Gas Cooled Reactor for HTGR-GT System

Yasushi MUTO,Shintaro ISHIYAMA,Kiyonobu YAMASHITA, Kazutaka OHASHI,Tetsuo NAKATA,Futoshi OKAMOTO

Doryoku, Enerugi Gijutsu Shinpojiumu koen ronbunshu/Doryoku, enerugi gijutsu no saizensen koen ronbunshu（2000）

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摘要

This paper describes a pebble-bed type nuclear reactor design of HTGR with gas-turbine plant. The main objectives of this design are to attain a thermal output of 400 MWt, whereas that of the previous design is only 300 MWt, without any changes of the core inlet/outlet temperature conditions and the material of the reactor pressure vessel. The outline of the reactor design and nuclear and thermal-hydraulic performance evaluation results are provided.

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