2115 超臨界圧水冷却炉炉心用候補材の高温強度と全面腐食特性

概要

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One of the major technical issues is development of materials for the supercritical-water cooled power reactor (SCPR) fuel claddings and core components. The materials will be used under the high-pressurized water in the temperature range of 573K-823K. Therefore, they should involve good properties of mechanical integrity, corrosion resistance and radiation damage. Technical issues of the material development were clarified from the literature survey of the material technologies for the fields of supercritical pressure fossil fired power plants, supercritical-water waste processing plants, and nuclear power plants. After that, test materials were nominated from austenitic and ferritic stainless steels, Ni-based alloys and Ti-based alloys. Tensile tests at 550℃ were conducted to evaluate the mechanical integrity of the materials under high temperature environments. General corrosion tests and 1 MeV electron irradiation tests were carried out under the SCPR core conditions, which were expected from the current research of the SCPR core design. The database will be applied to the screening of the most promising materials for the fuel claddings and to improvement of the SCPR system design. In this paper, the framework of the material development is introduced, and the data from general corrosion tests and electron irradiation tests are presented.
社団法人日本機械学会の論文
2003-08-05