A study on modeling and numerical simulation of extraction in the CMPO-TBP system
Creators
- 1. Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works
Description
A numerical simulation code for the TRUEX (Transuranium Extraction) process was developed. Concentration profiles of americium and europium were calculated for some experiments of the counter current extraction system those were carried out in CPF (Chemical Processing Facility) by using the code. Calculation profiles were in agreement with the experimental results. Operational conditions were also examined for the americium recovery experiment by the TRUEX process carried out in the Plutonium Fuel Center. It was shown that lowering the concentration of nitric acid in the scrub solution and decreasing the flow rate of solvent and strip solution was effective for improving the performance of the stripping step and reducing the volume of the waste solution. In order to find the optimum conditions for various experiments, this simulation code was modified to calculate the concentration profiles of other metal elements such as zirconium and iron and the effect of oxalic acid on the extraction behavior of the metal elements. The calculated concentration profiles of americium and europium were varied by this modification. In the experiment at CPF, the calculations were carried out to obtain recovery ratio of americium in the product stream with the amount of oxalic acid added to the process. This calculation result showed that it was possible to improve the performance of decontamination of fission products by increasing oxalic acid concentration added to the process. The calculation was also carried out for finding the optimum conditions of oxalic acid concentration added to the europium recovery process. (author)
Availability note (English)
Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781, JICST Service Homepage: www.jst.go.jp/EN/Additional details
Publishing Information
- Imprint Pagination
- 67 p.
- Report number
- JNC-TN--8400-2001-022
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33027397
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AMERICIUM; CMPO; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; EUROPIUM; EXTRACTION; OPTIMIZATION; OXALIC ACID; TBP; TRUEX PROCESS
- Descriptors DEC
- ACTINIDES; BUTYL PHOSPHATES; CARBOXYLIC ACIDS; DICARBOXYLIC ACIDS; ELEMENTS; ESTERS; METALS; ORGANIC ACIDS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXYGEN COMPOUNDS; PHOSPHINE OXIDES; PHOSPHINES; PHOSPHORIC ACID ESTERS; PHOSPHORUS COMPOUNDS; RARE EARTHS; REPROCESSING; SEPARATION PROCESSES; SIMULATION; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 29 refs., 33 figs., 7 tabs.