[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.5516/NET.2007.39.2.103

HTGR PROJECTS IN CHINA

Wu, Zongxin (Institute of Nuclear and New Energy Technology, Tsinghua University)
Yu, Suyuan (Institute of Nuclear and New Energy Technology, Tsinghua University)

Publication Information

Nuclear Engineering and Technology / v.39, no.2, 2007 , pp. 103-110 More about this Journal

Abstract

The High Temperature Gas-cooled Reactor (HTGR) possesses inherent safety features and is recognized as a representative advanced nuclear system for the future. Based on the success of the HTR-10, the long-time operation test and safety demonstration tests were carried out. The long-time operation test verifies that the operation procedure and control method are appropriate for the HTR-10 and the safety demonstration test shows that the HTR-10 possesses inherent safety features with a great margin. Meanwhile, two new projects have been recently launched to further develop HTGR technology. One is a prototype modular plant, denoted as HTR-PM, to demonstrate the commercial capability of the HTGR power plant. The HTR-PM is designed as $2{\times}250$ MWt, pebble bed core with a steam turbine generator that serves as an energy conversion system. The other is a gas turbine generator system coupled with the HTR-10, denoted as HTR-10GT, built to demonstrate the feasibility of the HTGR gas turbine technology. The gas turbine generator system is designed in a single shaft configuration supported by active magnetic bearings (AMB). The HTR-10GT project is now in the stage of engineering design and component fabrication. R&D on the helium turbocompressor, a key component, and the key technology of AMB are in progress.

Keywords

HTGR; HTR-PM; HTR-10GT; Helium -Gas Turbine;

Citations & Related Records

Times Cited By Web Of Science : 5 (Related Records In Web of Science)

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