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The Nuclear-Fuel Manufacturing Adaptability Study of UNH Crystal-Conversion Products

Yamasaki, Kazuhiko*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Kikuchi, Toshiaki*

Crystallization procedure is considered to have an adaptability to new reprocessing process based on the PUREX process because it has an advantage in recovering rather pure uranium from contaminated uranium solution without reagent. Hydrated uranyl nitrate (UNH) crystal from crystallization procedure is fed to the conversion process into UO2 for the fabrication of nuclear fuel. We have researched for denitration or conversion methods which is suited to UNH crystal and molten salt since. Due to the selection from some denitration or conversion methods, it is very important to research. an adaptability of the product from the denitration or conversion methods.In this study, we investigated some powder properties of the products, as important factors for nuclear -fuel-manufacturing, from the denitration or conversion methods. Next, we selected pelletizing process, viblo-packing fuel process and covered-particle fuel process as major manufacturing-process of nuclear fuel and research the conditions of uranyl oxide required from each processes. From the comparison between these conditions and the result from denitration or conversion methods, we estimated an adaptability of these methods to nuclear -fuel-manufacturing. As a result, we showed that freeze dry method, ADU and AUC method may be suited to pelletizing process. We also showed that electric reduction method, internal gelation method, and external gelation method may be suited to viblo-packing and covered-particle fuel process.

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