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Validation of solvent extraction scheme for the reprocessing of advanced heavy water reactor spent fuel using N,N-dihexyl octanamide as extractant / Neelam Kumari in Industrial & engineering chemistry research, Vol. 51 N° 44 (Novembre 2012) 

Public ISBD [article]  in Industrial & engineering chemistry research > Vol. 51 N° 44 (Novembre 2012) . - pp. 14535-14542 Titre : Validation of solvent extraction scheme for the reprocessing of advanced heavy water reactor spent fuel using N,N-dihexyl octanamide as extractant Type de document : texte imprimé Auteurs : Neelam Kumari, Auteur ; D. R. Prabhu, Auteur ; A. S. Kanekar, Auteur Année de publication : 2013 Article en page(s) : pp. 14535-14542 Note générale : Industrial chemistry Langues : Anglais (eng) Mots-clés : Fuel  Reactor  Heavy  water  Reprocessing  Solvent  extraction Résumé : Even though tri-n-butyl phosphate (TBP) has been the work horse for spent fuel reprocessing, some of its drawbacks are of major concern. Based on batch extraction studies, our group at Radiochemistry Division, BARC has proposed N,N-dihexyl octanamide (DHOA) as an alternative extractant to TBP for the reprocessing of three component Advanced Heavy Water Reactor (AHWR) spent fuels. To validate the batch data, twelve stage counter-current mixer settler runs were carried out on a simulated AHWR feed [∼2 g/L U + ∼2 g/L Pu + 100 g/L Th + 0.03 M HF + 0.1 M Al(NO3)3 at ∼ 3.5 M HNO3] (with a Pu tracer instead of 2 g/L; due to marginal variation in its extraction behavior) with 0.18 M TBP and 0.36 M DHOA/n-dodecane as extractants. Quantitative extraction of Pu and U was achieved in ∼S stages (maintaining volume ratio (O/A) as 1.1) leaving the bulk of thorium in the raffinate. Co-extracted thorium (∼4.5%) from the organic phase was scrubbed using 4 M HNO3. Partitioning of Pu from a loaded organic phase was carried out employing 0.5 M hydroxyl ammonium nitrate (HAN) at 2 M HNO3 as the strippant. Finally, uranium was stripped quantitatively using 0.01 M HNO3. The results clearly established the cocurrent studies using 0.36 M DHOA/n-dodecane as the extractant. The proposed flow sheet using 0.36 M DHOA/n-dodecane appears attractive with respect to the volume of the organic waste generated as compared to that of 0.18 M TBP/n-dodecane. Radiolytic degradation and hydrodynamic parameters of 0.36 M DHOA were also evaluated vis-à-vis 0.18 M TBP in n-dodecane. ISSN : 0888-5885 En ligne : http://cat.inist.fr/?aModele=afficheN&cpsidt=26620368 [article] Validation of solvent extraction scheme for the reprocessing of advanced heavy water reactor spent fuel using N,N-dihexyl octanamide as extractant [texte imprimé] / Neelam Kumari, Auteur ; D. R. Prabhu, Auteur ; A. S. Kanekar, Auteur . - 2013 . - pp. 14535-14542. Industrial chemistry Langues : Anglais (eng) in Industrial & engineering chemistry research > Vol. 51 N° 44 (Novembre 2012) . - pp. 14535-14542 Mots-clés : Fuel  Reactor  Heavy  water  Reprocessing  Solvent  extraction Résumé : Even though tri-n-butyl phosphate (TBP) has been the work horse for spent fuel reprocessing, some of its drawbacks are of major concern. Based on batch extraction studies, our group at Radiochemistry Division, BARC has proposed N,N-dihexyl octanamide (DHOA) as an alternative extractant to TBP for the reprocessing of three component Advanced Heavy Water Reactor (AHWR) spent fuels. To validate the batch data, twelve stage counter-current mixer settler runs were carried out on a simulated AHWR feed [∼2 g/L U + ∼2 g/L Pu + 100 g/L Th + 0.03 M HF + 0.1 M Al(NO3)3 at ∼ 3.5 M HNO3] (with a Pu tracer instead of 2 g/L; due to marginal variation in its extraction behavior) with 0.18 M TBP and 0.36 M DHOA/n-dodecane as extractants. Quantitative extraction of Pu and U was achieved in ∼S stages (maintaining volume ratio (O/A) as 1.1) leaving the bulk of thorium in the raffinate. Co-extracted thorium (∼4.5%) from the organic phase was scrubbed using 4 M HNO3. Partitioning of Pu from a loaded organic phase was carried out employing 0.5 M hydroxyl ammonium nitrate (HAN) at 2 M HNO3 as the strippant. Finally, uranium was stripped quantitatively using 0.01 M HNO3. The results clearly established the cocurrent studies using 0.36 M DHOA/n-dodecane as the extractant. The proposed flow sheet using 0.36 M DHOA/n-dodecane appears attractive with respect to the volume of the organic waste generated as compared to that of 0.18 M TBP/n-dodecane. Radiolytic degradation and hydrodynamic parameters of 0.36 M DHOA were also evaluated vis-à-vis 0.18 M TBP in n-dodecane. ISSN : 0888-5885 En ligne : http://cat.inist.fr/?aModele=afficheN&cpsidt=26620368