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Goto, Minoru; Shimakawa, Satoshi; Terada, Atsuhiko; Shibata, Taiju; Tachibana, Yukio; Kunitomi, Kazuhiko
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 5 Pages, 2011/09
The present study challenges the core design of a small-sized reactor for long refueling interval by increasing core size, fuel loading and fuel burn up compared with the High Temperature engineering Test Reactor (HTTR). The core burn-up calculation suggested that approximately 6 years of long refueling interval was found to be reasonably achieved with operational reactor power of 120 MWt.
Ohashi, Hirofumi; Sato, Hiroyuki; Tazawa, Yujiro; Yan, X.; Tachibana, Yukio; Kunitomi, Kazuhiko
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 10 Pages, 2011/09
JAEA has started a conceptual design of a small-sized HTGR for steam supply and power generation (HTR50S), of which reactor power is 50 MWt and the reactor outlet temperature is 750
C, to deploy the HTGR in developing countries at an early date (i.e., in the 2030s). The major specifications of the HTR50S were determined based on its design philosophy, which is to upgrade its performance and to reduce the cost by utilizing the knowledge obtained by the HTTR operation and the GTHTR300 design. The system design of HTR50s was performed to offer the capability of electricity generation, cogeneration of electricity and steam for a district heating and industries. The market potential for the small-sized HTGR in the developing countries was evaluated for the application of the electricity, process heat, district heating and pure water production. It was confirmed that there is enough market potential for the small-sized HTGR in the developing countries.
Kurata, Yuji; Yokota, Hitoshi*; Suzuki, Tetsuya*
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 7 Pages, 2011/09
Small and medium reactors using lead alloys as coolant are one of the promising reactor concepts with improved safety. This paper focuses on development of Al-alloy coating for nuclear systems using liquid lead-bismuth eutectic (LBE). Since corrosion attack becomes severe against steels at high temperatures, it is necessary to improve corrosion resistance. An Al-alloy coating method using Al, Ti and Fe powders, and laser beam heating has been developed. Main defects formed in an Al-powder-alloy coating process are surface defects and cracks. Conditions required to avoid these defects were found. According to results of the corrosion tests at 550 C in liquid LBE, the Al-alloy coating layers on 316SS protect severe corrosion attack observed in 316SS without coating. From the viewpoints of the soundness of coating layers and preservation of their corrosion resistance, it is estimated that the range of the adequate Al concentration in the coating layer is from 4 to 12 wt%.
