By International Atomic Energy Agency
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Extra resources for Safety related design and economic aspects of HTGRs : Proceedings of a technical committee meeting held in Beijing, China, 24 November 1998
Sample text
The HTR-10 test reactor is a test module for demonstrating the safety features of the modular HTGR design. The reference value of the HTR-10 reactor safety design to modular HTGR of commercial size is a worthwhile issue to be evaluated in the future along with the operational experience of the test reactor. 38 PRESENT ACTIVITY OF THE FEASIBILITY STUDY OF HTGR-GT SYSTEM Y. MUTO, Y. MIYAMOTO, S. SHIOZAWA Department of Advanced Nuclear Heat Technology, Oarai Research Establishment, Japan Atomic Energy Institute, Oarai, Ibaraki, Japan Abstract In JAERI a feasibility study of the High Temperature Gas-cooled Reactor - Gas Turbine (HTGR-GT) system has been carried out since January, 1997 as an assigned work by the Science and Technology Agency.
The Power Conversion System (PCS) is placed within the pressure vessel, connected with the reactor vessel by the cross vessel, and consists of the one-shaft vertical arranged turbomachine, recuperator, precooler, intercooler and internal gas ducts and supports. The turbomachine consists of gas turbine, electric generator, LP and HP compressors. The primary circuit helium coolant leaves the reactor core and through the hot gas duct inside of the cross vessel comes to the turbine inlet. The turbine rotates directly the low pressure and high pressure compressors.
In the second concept, a cylindrical partition plate is provided only at the top entrance section, where the gas temperature is low enough to use metallic material for the plate. Therefore the strength of partition plate is no longer of concern. In order to reduce the bypass flow through the central region, the size of graphite balls is reduced to half of that of the fuel balls. As the flow area in the central region is a third of the annular area and the pressure drop in the central region is four times larger than that at the annular region, the estimated bypass flow is only less than 10%.
Safety related design and economic aspects of HTGRs : Proceedings of a technical committee meeting held in Beijing, China, 24 November 1998 by International Atomic Energy Agency
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