Transuranium elements partition calculation code Advanced MIXSET for Purex process
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works
Description
Many solvent extraction studies of transuranium elements have been reported, but the partition profile of transuranium elements has been scarcely simulated. So, to simulate the partition profile of transuranium elements such as neptunium, americium and curium, transuranium elements partition calculation code, Advanced MIXSET has been developed. In the present study, distribution coefficients of transuranium elements such as Np(IV), Np(V), Np(VI), Am(III) and Cm(III) and the redox reactions of neptunium were rearranged numerically with the data in the published literatures. Advanced MIXSET has been made by reforming the previous Revised MIXSET to give an option to calculate transuranium elements partition in the Purex process. This Advanced MIXSET code has been verified to be useful by the good agreements between the simulated and the concentration profiles of neptunium recovery flowsheets of the PNC and Karlsruhe, respectively. (author)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 283 p.
- Report number
- PNCT--841-81-35
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13676180
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- AMERICIUM; COMPUTERIZED SIMULATION; CURIUM; DISTRIBUTION FUNCTIONS; M CODES; NEPTUNIUM; PARTITION; PUREX PROCESS; SOLVENT EXTRACTION; TRANSURANIUM ELEMENTS
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; ELEMENTS; METALS; REPROCESSING; SEPARATION PROCESSES; SIMULATION; TRANSPLUTONIUM ELEMENTS