Published July 2009 | Version v1
Journal article

Demonstration of pyropartitioning process by using genuine high-level liquid waste. Reductive-extraction of actinide elements from chlorination product

  • 1. Central Research Inst. of Electric Power Industry, Nuclear Technology Research Lab., Komae, Tokyo (Japan)
  • 2. Institute for Transuranium Elements, Karlsruhe (Germany)

Description

The pyropartitioning process separates the minor actinide elements (MAs) together with uranium and plutonium from the high-level liquid waste generated at the Purex reprocessing of spent LWR fuel and introduces them to metallic fuel cycle. For the demonstration of this technology, a series experiment using 520g of genuine high-level liquid waste was started and the conversion of actinide elements to their chlorides was already demonstrated by denitration and chlorination. In the present study, a reductive extraction experiment in molten salt/liquid cadmium system to recover actinide elements from the chlorination product of the genuine high-level liquid waste was performed. The results of the experiment are as following; 1) By the addition of the cadmium-lithium alloy reductant, almost all of plutonium and MAs in the initial high-level liquid waste were recovered in the cadmium phase. It means no mass loss during denitration, chlorination, and reductive-extraction. 2) The separation factor values of plutonium, MAs, and rare-earth fission product elements versus uranium agreed with the literature values. Therefore, actinide elements will be separated from fission product elements in the actual system. Hence, the pyropartitioning process was successfully demonstrated. (author)

Additional details

Publishing Information

Journal Title
Denryoku Chuo Kenkyusho Hokoku
Journal Issue
no.L08011
Journal Page Range
p. 1-4, 1-14
ISSN
1340-4652

Optional Information

Notes
29 refs., 16 figs., 4 tabs.