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Emerging Challenges
Published in Naosuke Itoigawa, Bernhard Wilpert, Babette Fahlbruch, Emerging Demands for the Safety of Nuclear Power Operations, 2004
In 1984, JCO received a license from the Japanese government nuclear safety regulatory body, allowing the production system facility to produce uranium dioxide powder or uranyl nitrate solution with an enrichment level of less than 20%. These products were to be utilized for fuel rods of Joyo, an experimental fast breeder reactor. As shown in Figure 10.1, the production process for the product solution of uranyl nitrate consisted of two parts. The first part entailed uranium oxide purification, which involved the processes of dissolution of triuranium octoxide (U3O8) powder, solvent extraction, precipitation, and calcination. After the process of uranium oxide purification, the second part was for producing the product solution of uranyl nitrate, which consisted of redissolution and bottling processes. It should be noted that the homogenization process had not been taken into account at that time. Although the pure uranyl nitrate solution storage tank was connected through pipes with the dissolving tank, it was intended to provide not for homogenization, but for the bypassing of the extraction column or for storage of a product just before bottling. Our analysis has revealed the need and importance of the storage function during the various processes for maintaining the flexibility of the workflow (Tanabe & Yamaguchi, 2001b).
The Environment Today
Published in Anco S. Blazev, Power Generation and the Environment, 2021
“Type A” packages are designed to withstand minor accidents and are used for medium-activity materials such as medical or industrial radioisotopes. Ordinary industrial containers are used for low-activity material such as U3O8.
Recent activities in the field of nuclear waste management
Published in Journal of Nuclear Science and Technology, 2019
Yoshiaki Sakamoto, Takumi Saito
For low-level wastes generating from uranium usage facilities, the treatment of solid and liquid uranium wastes was studied [4–6]. The uranium catalyst, which was used in several industrial fields, became problematic radioactive waste for the treatment and final disposal. Therefore, the dissolution and immobilization method of the spent uranium catalyst was studied and showed over 80% volume reduction and low leachability [4]. On the other hand, the basic treatment method based on the conversion of uranium catalyst of USb3O10 to U3O8 was studied [5]. As for liquid uranium wastes, uranium removal mechanism and performance using graphene oxides functionalized with diethylenetriaminepentaacetic phenylenediamine were shown to be highly efficient for the removal of uranium (VI) from aqueous solution [6].
Option values of quantity flexibility in nuclear fuel long-term contracts: an application of the least squares Monte Carlo
Published in Geosystem Engineering, 2020
We start with the dynamics of the uranium spot-market price. Specifically, we assume that the spot price S(t) of U3O8 uranium evolves exogenously and stochastically according to a geometric Brownian motion (GBM) with drift as follows: