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| DC Field | Value | Language |
|---|---|---|
| dc.contributor.author | Kumar, Shekhar | - |
| dc.contributor.author | Koganti, SB | - |
| dc.date.accessioned | 2013-10-29T11:24:21Z | - |
| dc.date.available | 2013-10-29T11:24:21Z | - |
| dc.date.issued | 2001-01 | - |
| dc.identifier.issn | 0975-0991 (Online); 0971-457X (Print) | - |
| dc.identifier.uri | http://hdl.handle.net/123456789/22840 | - |
| dc.description | 51-53 | en_US |
| dc.description.abstract | Stringent environmental norms require confinement of tritium and its proper disposal during solvent extraction operations of reprocessing. Current solvent extraction flowsheets, for reprocessing the spent nuclear fuel, have provision for tritium scrubbing from loaded solvent. Quantitative models for tritium distribution are not available in the literature. In this communication, an empirical model is reported for correlating the tritium distribution coefficient in nitric acid-30% TBP/n-dodecane system to aqueous nitric acid and free TBP. | en_US |
| dc.language.iso | en_US | en_US |
| dc.publisher | NISCAIR-CSIR, India | en_US |
| dc.rights |  CC Attribution-Noncommercial-No Derivative Works 2.5 India | en_US |
| dc.source | IJCT Vol.08(1) [January 2001] | en_US |
| dc.title | Modelling of tritium distribution coefficients in 30 Vol% TBP/n-dodecane/UO2(NO3) 2/ nitric acid system | en_US |
| dc.type | Article | en_US |
| Appears in Collections: | IJCT Vol.08(1) [January 2001] | |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| IJCT 8(1) 51-53.pdf | 482.32 kB | Adobe PDF | View/Open |
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