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Usuki, Toshiyuki; Yoshida, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko
no journal, ,
Minor actinides (MA) have lasting radio-toxicity. One of the possible ways to reduce radio-toxicity is transmutation of MA using nuclear reactors. Inert matrix (IM) is applied to host material for MA in transmutation. Silicon nitride (SiN) ceramics considered to be a candidate material of IM since it has a high thermal conductivity and shows good resistance to neutron irradiation. In this study, We proposed fabrication of silicon nitride ceramics based IMFs with Ce as simulating element and with magnesium silicates, i.e. enstatite (MgSiO), steatite (MgSiO) and forsterite (MgSiO), as additives. The sintered densities of SiN-based IMFs with forsterite was above 96 % theoretical 1723 K. Furthermore, The thermal conductivities of IMFs sintered at 1923 K were above 34 W/mK.
Honda, Masaki*; Sawa, Kazuhiro
no journal, ,
Japan can provide high quality fuel for high temperature-gas cooled reactors in commercial scale. Fabrication technologies, irradiation performance and irradiation test plan are introduced.
Fuketa, Toyoshi; Nagase, Fumihisa; Sugiyama, Tomoyuki; Amaya, Masaki
no journal, ,
The Japan Atomic Energy Agency (JAEA) performs the Advance Light Water Reactor Performance and Safety Research (ALPS) program in order to proceed a better understanding on behavior of high burnup fuels under accidental conditions and to provide database for regulatory judgment. JAEA launched the program in 2002, and extensive examinations including reactivity-initiated accident (RIA) studies and loss-of-coolant accident (LOCA) studies have been performed by using some unique facilities such as Nuclear Safety Research Reactor (NSRR) and Reactor Fuel Examination Facility (RFEF). High-duty operations including high burnup of fuel, power uprating and longer operation cycle are expected for efficient use of LWRs. In order to obtain the database on the behavior of the advanced fuels under accidental conditions, JAEA have started the second phase of the ALPS program (ALPS-II). The present paper describes key observations in the ALPS-I and an outline of the ALPS-II.
Koyama, Shinichi
no journal, ,
Property of Am-containing MOX fuel is described. Firstly, production of minor actinides and its fundamental property are introduced. Then, fabrication technology for low and high Am-containing MOX fuels is explained. Finally, the irradiation behavior is introduced.