Filters
Results 1 - 10 of 2414
Results 1 - 10 of 2414.
Search took: 0.03 seconds
Sort by: date | relevance |
AbstractAbstract
[en] Radiochemical separations have traditionally been performed by various techniques which could be classified into one of three general classes of chemical separations. They are: precipitation separations, liquid-liquid separations, and ion-exchange separations. To differing degrees all of the above suffer from various issues that make their inclusion as part of modern radiochemical laboratory methodology problematic. The two main issues are that the techniques are typically time consuming and they tend to generate relatively large quantities of waste in an era when waste minimization is being vigorously pursued. A relatively new type of separation technique has been used in the past five years that is both more timely in its use and lends itself to the pursuit of minimum waste volumes in the laboratory. That technique is extraction chromatography. Here, the selectivity of solvent extraction is combined with the simplicity of column chromatography. Incorporation of selective solvents such as crown ethers allows the radiochemist to perform separations rapidly with minimum waste volumes generated for disposal by the laboratory. Examples of extraction chromatography using crown ethers will be discussed
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Riekkinen, I.; Pulli, S.; Kylloenen, J.; Jaakkola, T.
Proceedings of the 8. Nordic seminar on radioecology2002
Proceedings of the 8. Nordic seminar on radioecology2002
AbstractAbstract
[en] The concentrations of transuranic elements in the environment are usually extremely low. Special procedures are needed for preconcentration and separation of these nuclides from various matrices and from other actinides. Traditional ion exchange methods have been used for separation of Pu and Am for decades. In recent years extraction chromatography methods based on new materials have been developed. These new methods are simpler and faster to use than the conventional methods based on ion exchange, especially for americium. In this work application of Eichrom's extraction chromatography resins (UTEVA, TRU, TEVA) and an anion exchange resin (Dowex lx4) were studied for the separation of Pu and Am from different natural matrices. (au)
Primary Subject
Source
Ilus, E. (ed.) (STUK (FI)); Nordisk Kernesikkerhedsforskning, Roskilde (Denmark); 233 p; ISBN 87-7893-126-6;
; Apr 2002; p. 210-213; 8. Nordic seminar on radioecology; Rovaniemi (Finland); 25-28 Feb 2001

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The Radiochemical Engineering Development Center at Oak Ridge National Laboratory processes irradiated targets to recover the transplutonium actinides for research and industrial users. In a typical processing campaign, dekagram quantities of curium are recovered for recycle into targets for subsequent irradiation and processing; decigram quantities of californium are recovered for fabrication into neutron sources; and milligram quantities of einsteinium and berkelium as well as picogram quantities of fermium are recovered for distribution to the research community. The transcurium actinides are separated in a series of chromatographic elutions using a cation-exchange resin and ammonium α-hydroxyisobutyrate as the eluant. The fermium fraction from these final purification runs still contains significant amounts of rare earth fission products, such as yttrium, dysprosium, and holmium. In the most recent campaign, a process using a TEVA trademark resin extraction chromatography column was developed and tested to determine its effectiveness in providing a fermium product free of rare earth fission products. Gamma spectroscopy indicated that dysprosium and holmium were reduced to levels less than minimum detectable limits and that only 0.07 pg of 91Y remained in the final fermium product, which contained 0.5 pg of 257Fm. An overall decontamination factor of ∼103 was achieved for fission product removal
Primary Subject
Source
9. symposium on separation science and technology for energy applications; Gatlinburg, TN (United States); 22-26 Oct 1995; CONF-951057--
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Separation de l'uranium de ses impuretes par chromatographie liquide
Primary Subject
Source
CEA, 75 - Paris (France). Commission d'Etablissement des Methodes d'Analyse (CETAMA); p. 181-182; nd; p. 181-182; Meeting on uranium analysis; Saclay, France; 17 - 18 Dec 1975; Published in summary form only.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Eschrich, H.; Drent, W.
European Company for the Chemical Processing of Irradiated Fuels, Mol (Belgium)1971
European Company for the Chemical Processing of Irradiated Fuels, Mol (Belgium)1971
AbstractAbstract
No abstract available
Primary Subject
Source
Jun 1971; 131 p; 381 refs.
Record Type
Report
Literature Type
Bibliography
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Brahmmananda Rao, C.V.S.; Jayalakshmi, S.; Sivaraman, N.; Vasudeva Rao, P.R., E-mail: brahma@igcar.gov.in
Proceedings of the twelfth DAE-BRNS national symposium on nuclear and radiochemistry2015
Proceedings of the twelfth DAE-BRNS national symposium on nuclear and radiochemistry2015
AbstractAbstract
[en] Extraction chromatographic studies of XAD-7 impregnated with unsymmetrical phosphonate, Dibutylamyl phosphonate (DBAP) for the extraction of uranium and thorium were carried out. The present studies indicate that uranium and thorium in 4 M HNO3 were successively loaded and eluted with 0.01 M nitric acid. (author)
Primary Subject
Source
Deb, S.B.; Ramakumar, K.L. (Radioanalytical Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)) (eds.); Kannan, S. (ed.) (Fuel Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)); Mukerjee, S.K. (ed.) (Product Development Division, Bhabha Atomic Research Centre, Mumbai (India)); Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India); Indian Association of Nuclear Chemists and Allied Scientists, Mumbai (India); 700 p; 2015; p. 138-139; NUCAR-2015: 12. DAE-BRNS national symposium on nuclear and radiochemistry; Mumbai (India); 9-13 Feb 2015; 4 refs., 4 figs.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In order to enrich 10B, 40 meter band migration of boric acid-mannitol with hydrochloric acid solution was performed by inverse frontal chromatography on a porous, 25% crosslinked, 38% quaternized 4-vinylpyridine-divinylbenzene resin. The maximum enrichment (RL) of 10B was 94.15%. The overall process parameters, namely slope coefficient (k) and separation coefficient (e), were found to be 0.1282 cm-1 and 0.02967, respectively
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Figols, M.E.B.
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1991
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1991
AbstractAbstract
[en] Neptunium and uranium behavior in extraction chromatography system, aiming the separation of microquantities of neptunium from uranyl nitrate solutions is described. Tri-n-octylamina (TOA), tri-n-butylphosphate (TBP), thenoyltrifluoroacetone (TTA) as stationary phase, alumina, Voltalef-UF-300, silica as support material were verified. The impregnation conditions as well as the best stationary phase/support material ratio were established. TBP/alumina, TBP/Voltalef and TOA/alumina system were selected to uranium and neptunium separation studies. In the system using TBP as extractant agent uranium and neptunium separation was reached by selective elution after the retention of both elements on the column. U-Np separation by selective retention of Np was possible with TOA system. The capacity of the column was the 66.6 mg U/mL and 191.6mg U/mL for the TBP/alumina and TBP/Voltalef systems, respectively. An application of extraction chromatography system in the final phase of irradiated uranium treatment process is proposed. (author)
Original Title
Separacao de tracos de neptunio de solucoes de uranio por cromatografia de extracao
Primary Subject
Source
1991; 103 p; Tese (M.Sc.).
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Report Number
Country of publication
LanguageLanguage
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] 1-H-1-(3-[18F]fluoro-2-hydroxypropyl)-2-nitroimidazole ([18F]FMISO), is the most used hypoxia-imaging agent in oncology and we have recently reported a fully automated procedure for its synthesis using the Nuclear Interface FDG module and a single neutral alumina column for purification. Using 1-(2'-nitro-1'-imidazolyl)-2-O-tetra-hydropyranyl-3-O- toluenesulfonylpropanediol (NITTP) as the precursor, we have investigated the yield of [18F]FMISO using different reaction times, temperatures, and the amount of precursor. The overall yield was 48.4 ± 1.2% (n = 3), (without decay correction) obtained using 10 mg NITTP with the radio-fluorination carried out at 145 deg C for 3 min followed by acid hydrolysis for 3 min at 125 deg C in a total synthesis time of 32 ± 1 min. Increasing the precursor amount to 25 mg did not improve the overall yield under identical reaction conditions, with the decay uncorrected yield being 46.8 ± 1.6% (n = 3), but rather made the production less economical. It was also observed that the yield increased linearly with the amount of NITTP used, from 2.5 to 10 mg and plateaued from 10 to 25 mg. Radio-fluorination efficiency at four different conditions was also compared. It was also observed by radio thin layer chromatography (radio-TLC) that the duration of radio-fluorination of NITTP, not the radio-fluorination temperature favoured the formation of labeled thermally degraded product, but the single neutral alumina column purification was sufficient enough to obtain [18F]FMISO devoid of any radiochemical as well as cold impurities. (author)
Primary Subject
Source
21 refs.
Record Type
Journal Article
Journal
Journal of Radioanalytical and Nuclear Chemistry; ISSN 0236-5731;
; CODEN JRNCDM; v. 286(1); p. 241-248

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rodrigues, A.M.; Bustillos, J.O.W.V.
Bahia Univ., Salvador, BA (Brazil). Inst. de Quimica1989
Bahia Univ., Salvador, BA (Brazil). Inst. de Quimica1989
AbstractAbstract
[en] Published in summary form only
Original Title
Determinacao do teor de hidrogenio no zirconio metalico
Primary Subject
Source
1989; 1 p; 5. Brazilian Meeting on Analytical Chemistry; Salvador, BA (Brazil); 4-6 Sep 1989
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
LanguageLanguage
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |