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Yadav AG, Mohapatra PK, Valsala TP, Sathe DB, Bhatt RB. Highly efficient separation of Am(III) and Pu(IV) from lean feeds and soil using an extraction chromatographic resin containing a diglycolamide in an ionic liquid. J Chromatogr A 2023; 1707:464299. [PMID: 37597478 DOI: 10.1016/j.chroma.2023.464299] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/10/2023] [Accepted: 08/12/2023] [Indexed: 08/21/2023]
Abstract
A TODGA based extraction chromatographic resin containing an ionic liquid was used for the separation of actinide ions such as Am3+ and Pu4+ from samples such as lean effluents emanating from laboratory waste, environmental water as well as soil samples adjacent to a nuclear plant site. The methodology involved feed adjustment to 3 M HNO3 followed by conditioning of the column, loading, washing (3 M HNO3), and elution of the actinide ions. The elution of Am3+ was done using EDTA in a buffered medium (1 M guanidine carbonate) while that of Pu4+ was carried out using a mixture of 0.5 M oxalic acid and 0.5 M HNO3. The elution peaks were sharp with almost no tailing suggesting the efficiency of the separation method. The results obtained were compared with the literature results which suggested the high efficiency of the present method.
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Affiliation(s)
- Akalesh G Yadav
- Advanced Fuel Fabrication Facility, Nuclear Recycles Board, Tarapur, Maharashtra 401502, India; Homi Bhabha National Institute, Anushakti Nagar, Mumbai 400094, India
| | - Prasanta K Mohapatra
- Homi Bhabha National Institute, Anushakti Nagar, Mumbai 400094, India; Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085, India.
| | - Thichur P Valsala
- Advanced Fuel Fabrication Facility, Nuclear Recycles Board, Tarapur, Maharashtra 401502, India
| | - Darshan B Sathe
- Advanced Fuel Fabrication Facility, Nuclear Recycles Board, Tarapur, Maharashtra 401502, India
| | - Raj B Bhatt
- Advanced Fuel Fabrication Facility, Nuclear Recycles Board, Tarapur, Maharashtra 401502, India
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Pant AD, Ruhela R, Limje C, Anil Kumar S, Singh AK, Kumar SA, Sugandhi S, Kain V, Tomar BS. Evaluation of BenzoDODA grafted polymeric resin for rapid and reliable assaying of plutonium in sediment samples. JOURNAL OF ENVIRONMENTAL RADIOACTIVITY 2021; 234:106620. [PMID: 33984799 DOI: 10.1016/j.jenvrad.2021.106620] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 02/20/2021] [Revised: 04/02/2021] [Accepted: 04/08/2021] [Indexed: 06/12/2023]
Abstract
The paper reports a new rapid radioanalytical procedure for the determination of plutonium (Pu) in sediments by solid phase extraction chromatography (SPEC) using Bis-(2-ethylhexyl) carbamoyl methoxy phenoxy-bis-(2-ethylhexyl) grafted resin, abbreviated as Benzodioxodiamide (BenzoDODA) grafted resin. The resin was synthesized and evaluated for its sorption behaviour towards Pu in batch and column mode to determine its efficacy for selective recovery of Pu from sediment samples. The analytical procedure was based on the radiochemical separation of samples by acid digestion, followed by preconcentration of actinides by co-precipitation with Fe(OH)3 and finally selective recovery of Pu by SPEC using a column filled with BenzoDODA grafted resin. Pu was then radiometrically assayed by preparing alpha disc sources with electro-deposition followed by alpha spectrometry. The method was further validated with IAEA reference materials. This method gives reliable and reproducible results for the activity concentration of Pu in sediment samples within 24 h.
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Affiliation(s)
- Amar D Pant
- Radiation Safety Systems Division, Bhabha Atomic Reseach Centre, Mumbai, 400085, India; Homi Bhabha National Institute, Mumbai, 400094, India
| | - R Ruhela
- Materials Processing and Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, 400085, India; Homi Bhabha National Institute, Mumbai, 400094, India.
| | - C Limje
- Materials Processing and Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, 400085, India
| | - S Anil Kumar
- Radiation Safety Systems Division, Bhabha Atomic Reseach Centre, Mumbai, 400085, India
| | - A K Singh
- Materials Processing and Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, 400085, India
| | - Suja A Kumar
- Radiation Safety Systems Division, Bhabha Atomic Reseach Centre, Mumbai, 400085, India
| | - S Sugandhi
- Environmental Monitoring and Assessment Division, Bhabha Atomic Research Centre, Mumbai, 400085, India
| | - V Kain
- Materials Processing and Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, 400085, India
| | - B S Tomar
- Homi Bhabha National Institute, Mumbai, 400094, India
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Zheltonozhskaya MV, Zheltonozhsky VA, Vlasova IE, Kuzmenkova NV, Kalmykov SN. The plutonium isotopes and strontium-90 determination in hot particles by characteristic X-rays. JOURNAL OF ENVIRONMENTAL RADIOACTIVITY 2020; 225:106448. [PMID: 33075716 DOI: 10.1016/j.jenvrad.2020.106448] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 06/26/2020] [Revised: 09/16/2020] [Accepted: 10/12/2020] [Indexed: 06/11/2023]
Abstract
This paper reports the developed non-destructive methods for the plutonium isotopes and strontium-90 content determination in hot particles and other samples. The proposed methods are based on the measurement of the characteristic X-rays accompanying the decay of these radionuclides. For hot particles of NPP accident origin, the proposed method's error limits are 10-15% for hot particles (samples) with activity above 100 Bq and 15-20% for hot particles (samples) with activity less than 100 Bq. For explosive particles, the determination accuracy is 10-15% for activity more than 5 Bq and 20-30% for 0.1-5 Bq activity. The accuracy of the proposed method for determining 90Sr in samples with its specific content of more than 104 Bq/sample is 5%, with ~102 Bq/sample its content is 15-20%. The cost of one sample measurement and the processing time of these methods are significantly reduced compared to traditional studies. The proposed methods are reasonably simple measurement methods and can be carried out even in the field condition. They open up new possibilities for the quick search and study of hot particles and environmental samples.
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Affiliation(s)
| | | | - I E Vlasova
- Lomonosov Moscow State University, Russian Federation
| | | | - S N Kalmykov
- Lomonosov Moscow State University, Russian Federation
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