Recently, there has been increasing demand on finding new solid electrolytes based on glassy material, due to their potential applications for solid state rechargeable battery. Superionic conducting glasses have many advantageous compared with the crystalline, or composite electrolytes, such as easy in preparation, low melting point, no grain broundary, wide composition range and easy to be formed as thin film. Among superionic glasses, the family of silver phosphate glasses (AgI) x (AgPO 3 ) 1-x and lithium phosphate glasses (LiI) x (LiPO 3 ) 1-x , are the most interested materials to be investigated. Many experiments have been performed to investigate the properties of those materials. This paper will review the recent results of the lithium glasses (LiI) x (LiPO 3 ) 1-x , such as the preparation, appearance, structure, electrical and thermal properties. The x-ray data shows the precipitate occured at x=0.4, indicating the solubility limit of (LiI) x (LiPO 3 ) 1-x was reached at this composition. The microstructure data observed by SEM showed the different area between the smooth surface for x=0.3 and appearance of cluster at x=0.4. Comparison between glassy LiPO 3 and (LiI) 0.3 (LiPO 3 ) 1-x as the result of Raman spectra analysis, suggested a new feature at around 1000 cm -1 , indicating the depolymerization of the non bridging oxygen, due to the presence of LiI component. The room temperature conductivities of (LiI) x (LiPO 3 ) 1-x with x=0.3 and 0.4 are 2.7x10 -6 and 8.8x10 -7 S/cm, respectively, which are 3 orders of magnitudes higher than the undoped glass LiPO 3 . In general, the silver glass has better ionic conductivity than the lithium glass; but in application the lithium battery has better performance and produces higher voltage.

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SummaryComparison of uranium plutonium nitride and thorium nitride fuel for 500 MWth gas-cooled fast reactor has been done. Gas-cooled fast reactor is one type of generation IV reactor that can be operated in high temperature. Due to the high temperature, it can be used in hydrogen production. In this study, we compare the neutronic analysis of two fuel types, ie, uranium nitride fuel (U,Pu)N and thorium nitride fuel (Th,U233)N. The neutronic calculation uses SRAC2006 code system, and the data libraries use JENDL4.0.First, the fuel pin calculation (PIJ calculation) has been done to take the macro data that are used in CITATION calculation. Both uranium and thorium fuel use heterogeneous configuration with 3 variation fuel in the core. F1 is located in the central core, F2 middle core, and F3 outer core.The variation of fuel fraction is 40% until 65%, cladding 10%, and coolant 25% until 40%. For (U,Pu)N fuel, the diameter of the active core is 220 cm, and the height of the active core is 110 cm. And for (Th,U233)N, the diameter of the active core is 250 cm and the height of the active core is 150 cm. The reflector radial-axial width is 50 cm. For uranium plutonium nitride fuel, the type of the fuel in one core is varied; ie, F1 is 8%, F2 is 10%, and F3 is 12%. For thorium nitride fuel, the type of the fuel in one core also varied; ie, F1 is 7.8%, F2 is 8%, and F3 is 8.8%. The optimum value of thorium nitride is when fuel fraction of region F1 = 60%, F2 = 57.5%, F3 = 60%, the burn up time up to 20 years without refueling, max k-eff value is 1.0109, and max excess reactivity value is 1.08%. Neutronic analysis shows that both uranium and thorium fuel have excess reactivity value less than 2% but thorium fuel has excess reactivity less than uranium nitride fuel.Uranium fuel has better breeding capability than thorium fuel. Therefore, it is better to use uranium fuel for fast reactor like GFR, which has high breeding capability.