HTGR Knowledge Base

Conference Article: Study of Fission Product Release, Plate-out and Maintenance in Helium Turbomachinery

Y. Muto, S.Ishtyama, S.Shiozawa, Japan Atomic Energy Research Institute, Oarai-machi, Ibaraki-ken, Japan

Abstract

A feasibility study of HTGR-GT has been conducted in JAERI, as an assigned work by the Science and Technology Agency in Japan. So far, the conceptual or preliminary designs of 600, 400 and 300MW(t) power plants have been completed. The block type core and pebble-bed core have been selected in 600MW(t) and 400/300MW(t), respectively. In this plant concept, maintenance of turbine rotor is one of the most important issues.
This paper describes the results of preliminary estimation of generation in the fuel, release into coolant and plate out on the components of 137Cs and 110mAg. In addition, maintenance method of turbine rotor is discussed.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
IAEA Technical Committee Meeting on “Gas Turbine Power Conversion Systems for Modular HTGRs”, held from 14-16 November 2000 in Palo Alto, California
International Atomic Energy Agency, Vienna (Austria). Technical Working Group on Gas-Cooled Reactors
IAEA-TECDOC--1238, pp:114-137