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Ukai, Shigeharu*; Ono, Naoko*; Otsuka, Satoshi
Comprehensive Nuclear Materials, 2nd Edition, Vol.3, p.255 - 292, 2020/08
Fe-Cr-based oxide dispersion strengthened (ODS) steels have a strong potential for high burnup (long-life) and high-temperature applications typical for SFR fuel cladding. Current progress in the development of Fe-Cr-based ODS steel claddings is reviewed, including their relevant mechanical properties, e.g. tensile and creep rupture strengths in the hoop directions. In addition, this paper reviewed the current research status on corrosion resistant Fe-Cr-Al-based ODS steel claddings, which are greatly paid attention recently as the accident tolerant fuel claddings for the light water reactor (LWR) and also as the claddings of the lead fast reactors (LFR) utilizing Pb-Bi eutectic (LBE) coolant.
Minato, Kazuo; Ogawa, Toru
Comprehensive Nuclear Materials, 3, p.215 - 236, 2012/03
TRISO coated particle fuel has been developed for the high temperature gas-cooled reactors, which consists of microspherical fuel kernel and coating layers of pyrolytic carbon and silicon carbide. To improve the high temperature stability, the resistance to the chemical attack by fission products and the retention of fission products of the TRISO coated particle fuels, several types of advanced fuels were proposed and tested. Coated particle fuels for fast reactors were also proposed and tested. In this chaper, fuel designs, fabrications, characterization techniques and fuel performance of these advanced coated particle fuels are systematically described.
Arai, Yasuo
Comprehensive Nuclear Materials, 3, p.41 - 54, 2012/03
Development of nitride fuel was extensively reviewed in this paper, which will be published in the Comprehensive Nuclear Materials. Characteristics of nitride fuel and history of the R&D were described in the introductive chapter. In the chapter of fabrication, nitride fuel preparation by carbothermic reduction and its sintering behavior were centered on the chapter. In the chapter of irradiation behavior, results of the irradiation tests performed so far were reviewed and the in-pile behavior of nitride fuel was described. Furthermore, in the chapter of reprocessing, hydrochemical and pyrochemical reprocessing technologies of nitride fuel were briefly explained. Outlook of nitride fuel was given in the last chapter. On the other hand, physical, chemical and thermodynamic properties of nitride fuel will be reviewed in another part of the Comprehensive Nuclear Materials.
