Actinide Separations by James D. Navratil and Wallace W. Schulz (Eds.)

By James D. Navratil and Wallace W. Schulz (Eds.)

content material: Neptunium (V) anionic alternate in sulfate-sulfuric acid options / J. Rego, J. Garrison, and R. Carver --
restoration of plutonium lines from nitric acid-fluorhydric acid suggestions through sorption onto alumina / J. Adroaldo De Araújo and Alcídio Abrão --
program of inorganic sorbents in actinide separations methods / Wallace W. Schulz, John W. Koenst, and David R. Tallant --
Transplutonium parts construction software : extraction chromatographic procedure for plutonium irradiated goals / J. Bourges, C. Madic, and G. Koehly --
Plutonium peroxide precipitation : evaluate and present examine / P.G. Hagan and F.J. Miner --
Actinide extractants : improvement, comparability, and destiny / R.R. Shoun and W.J. McDowell --
Demonstration of the potential of designing extractants with preselected extraction houses : attainable software to reactor gas reprocessing / G.W. Mason and H.E. Griffin --
Solvent extraction of transplutonium parts from acid suggestions by means of polydentate impartial organophosphorus compounds and from alkaline options by means of quarternary ammonium bases and through alkylpyrocatechols / B.F. Myasoedov, M.K. Chmutova, and Z.K. Karalova --
The extraction of uranium (VI) from sulphuric acid ideas by means of tri-n-octylphosphine oxide / Taichi Sato --
homes and makes use of of nitrogen and sulfur donors ligands in actinide separations / C. Musikas, G. Le Marois, R. Fitoussi, and C. Cuillerdier --
The "Cleanex" method : a flexible solvent extraction procedure for restoration and purification of lanthanides, americium, and curium / John E. Bigelow, Emory D. Collins, and Lester J. King --
Americium-curium separation via selective extraction of hexavalent americium utilizing a centrifugal contactor / C. Musikas, M. Germain, and A. Bathellier --
nationwide software for pyrochemical and dry processing of spent reactor gas / C.H. Bean and M.J. Steindler --
Pyrochemical coprocessing of uranium dioxide-plutonium dioxide LMFBR gas by means of the salt delivery process / James B. Knighton and Charles E. Baldwin --
A nonaqueous reprocessing technique for thorium-based fuels / J.K. Bates, L.J. Jardine, and M. Krumpelt --
AIROX dry pyrochemical processing of oxide fuels : a proliferation-resistant reprocessing procedure / L.F. Grantham, R.G. Clark, R.C. Hoyt, and J.R. Miller --
Molten salt oxidation-reduction procedures for gas processing / L.G. Morgan, L.L. Burger, and R.D. Scheele --
Photochemistry of the actinides / L.M. Toth, J.T. Bell, and H.A. Friedman --
program of photochemical suggestions to actinide separation tactics / G.L. Depoorter and C.K. Rofer-Depoorter --
Plutonium partitioning equipment in strength reactor gas reprocessing / Alfred Schneider and Barry G. Wahlig --
improvement of the electropulse column for uranium-plutonium partition within the AGNS reprocessing plant / A.F. Cermak and R.G. Spaunburgh --
Electroredox approaches for plutonium in strength reactor gasoline reprocessing / Franz Baumgärtner, Hubert Goldacker, and Helmut Schmieder --
The separation of uranium and plutonium by way of electrolytic relief within the purex procedure / He Jian-Yu, Zhang Qing-Xuan, and Lo Long-Jun --
experiences on actinides separation in JAERI / Tomitaro Ishimori --
Heavy aspect separation for thorium-uranium-plutonium fuels / G.R. furnish, W.W. Morgan, K.K. Mehta, and F.P. Sargent --
advancements in thorium-uranium separation within the acid-thorex approach / Glen E. Benedict --
Actinide partitioning flowsheets / D.D. Tedder, B.C. Finney, and J.O. Blomeke --
Flowsheet improvement paintings on the Idaho Chemical Processing Plant for the partitioning of actinides from acidic nuclear waste / L.D. McIsaac, J.D. Baker, J.F. Krupa, D.H. Meikrantz, and N.C. Schroeder --
restoration of derivative actinides from strength reactor fuels and construction of warmth resource isotopes / G. Koch --
Separation of actinides from purex-type excessive lively waste raffinates : improvement of experimental reports at JRC-ISPRA institution / L. Cecille, H. Dworschak, F. Girardi, B.A. Hunt, F. Mannone, and F. Mousty --
removing of americium and curium from high-level wastes / W.D. Bond and R.E. Leuze --
Americium restoration and purification at Rocky residences / James D. Navratil, Larry L. Martella, and Gary H. Thompson --
The extraction of DBP and MBP from actinides : program to the restoration of actinides from TBP-sodium carbonate scrub answer / E.P. Horwitz, G.W. Mason, C.A.A. Bloomquist, R.A. Leonard, and G.J. Bernstein --
Dissolution of plutonium dioxide : a severe assessment / Jack L. Ryan and Lane A. Bray --
fresh Savannah River adventure and improvement with actinide separations / M.C. Thompson, G.A. Burney, and J.M. McKibben --
Separation of long-lived [alpha]-emitters from hugely radioactive ideas within the thorium-uranium gas cycle / U. Wenzel, C.L. Branquinho, D. Herz, and G. Ritter --
Laboratory and pilot plant reviews on conversion of uranyl nitrate to uranium hexafluoride / I.J. Urza and D.C. Kilian --
Separation of actinides from excessive lively waste through counter present ion migration / B.A. Bilal, F. Herrmann, okay. Metscher, B. Mühlig, Ch. Reichmuth, and B. Schwarz --
Polymolybdates as plutonium (IV) hosts / R.A. Penneman, R.G. Haire, and M.H. Lloyd.

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Actinide Separations

Content material: Neptunium (V) anionic alternate in sulfate-sulfuric acid ideas / J. Rego, J. Garrison, and R. Carver -- restoration of plutonium lines from nitric acid-fluorhydric acid suggestions by way of sorption onto alumina / J. Adroaldo De Araújo and Alcídio Abrão -- program of inorganic sorbents in actinide separations tactics / Wallace W.

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14. 15. 16. 17. 18. 19. RECEIVED July 2, 1979. ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. 4 Transplutonium Elements Production Program Extraction Chromatographic Process for Plutonium Irradiated Targets J. B O U R G E S , C . M A D I C , and G . P. Ν 6-92260 Fontenay-aux-Roses, France The French transplutonium elements production program (essen­ tially Am and Cm) is based on the treatment of plutonium­ -aluminum alloy targets irradiated in the Celestin reactors at Mar­ coule.

ACS Symposium Series; American Chemical Society: Washington, DC, 1980.

The s e p a r a t i v e p e r f o r m a n c e s o f t h e t h r e e s y s t e m s , b a s e d o n t h e u s e o f t h e c o m p l e x a n t DTPA a r e g r o u p e d i n T a b l e I I I . I n a l l c a s e s i t was o b s e r v e d t h a t t h e s e p a ­ ration factors α = D ( L n ) . D ( A m ) were s h a r p l y h i g h e r i n t h e p r e s e n c e o f D T P A . The T a l s p e a k p r o c e s s a c h i e v e s good l a n t h a n i d e / t r a n s p l u t o n i u m s e p a r a t i o n , w h e r e a s t h e two r e m a i n i n g s y s t e m s o n l y a c h i e v e good s e p a r a t i o n o f t r i v a l e n t a c t i n i d e s f r o m l i g h t l a n t h a n i d e s i n c l u d i n g e u r o p i u m w i t h TBP prometheum w i t h TLAHNO 3 .

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