Published 2020 | Version v1
Journal article

Application of fluoride volatility method to the spent fuel reprocessing

  • 1. Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki (Japan)
  • 2. Hitachi, Ltd., Hitachi, Ibaraki (Japan)

Description

An advanced reprocessing system has been developed to treat various SF (spent fuels): spent UO2 and MOX (mixed oxide) fuels from LWR (light water reactor) and MOX fuel from FR (fast reactor). The system consists of SF fluorination to separate most U (uranium) as volatile UF6, dissolution of solid residue containing Pu (plutonium), FP (fission products), MA (minor actinides) and partial U by nitric acid, and Pu+U separation from FP and MA by conventional solvent extraction. Gaseous UF6 is purified by the thermal decomposition and the adsorption of volatile PuF6 and adsorption of other impurities. This system is a hybrid process of fluoride volatility and solvent extraction and called FLUOREX. Fluorination of most U in the early stage of the reprocessing process is aimed at sharply reducing the amount of SF to be treated in the downstream aqueous steps and directly providing purified UF6 for the enrichment process without conversion. The FLUOREX can flexibly adjust the Pu/U ratio, rapidly separate UF6 and economically treat aqueous Pu+U. These features are especially suitable for the transition period fuel cycle from LWR to FR. This paper summarizes the feasibility confirmation results of FLUOREX. (author)

Availability note (English)

Available from https://doi.org/10.1080/00223131.2019.1651230

Additional details

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo) (Online)
Journal Volume
57
Journal Issue
1
Journal Page Range
p. 49-56
ISSN
1881-1248

Optional Information

Notes
12 refs., 8 figs., 1 tab.