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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 strains from nitric acid-fluorhydric acid strategies via sorption onto alumina / J. Adroaldo De Araújo and Alcídio Abrão --
program of inorganic sorbents in actinide separations procedures / Wallace W. Schulz, John W. Koenst, and David R. Tallant --
Transplutonium parts creation software : extraction chromatographic method for plutonium irradiated objectives / J. Bourges, C. Madic, and G. Koehly --
Plutonium peroxide precipitation : evaluation 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 homes : attainable program to reactor gas reprocessing / G.W. Mason and H.E. Griffin --
Solvent extraction of transplutonium components from acid options by means of polydentate impartial organophosphorus compounds and from alkaline options by means of quarternary ammonium bases and via alkylpyrocatechols / B.F. Myasoedov, M.K. Chmutova, and Z.K. Karalova --
The extraction of uranium (VI) from sulphuric acid suggestions via tri-n-octylphosphine oxide / Taichi Sato --
houses 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" technique : a flexible solvent extraction strategy for restoration and purification of lanthanides, americium, and curium / John E. Bigelow, Emory D. Collins, and Lester J. King --
Americium-curium separation by way of 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 gasoline / C.H. Bean and M.J. Steindler --
Pyrochemical coprocessing of uranium dioxide-plutonium dioxide LMFBR gas through the salt shipping technique / James B. Knighton and Charles E. Baldwin --
A nonaqueous reprocessing strategy for thorium-based fuels / J.K. Bates, L.J. Jardine, and M. Krumpelt --
AIROX dry pyrochemical processing of oxide fuels : a proliferation-resistant reprocessing technique / L.F. Grantham, R.G. Clark, R.C. Hoyt, and J.R. Miller --
Molten salt oxidation-reduction procedures for gasoline 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 --
software of photochemical suggestions to actinide separation approaches / G.L. Depoorter and C.K. Rofer-Depoorter --
Plutonium partitioning equipment in energy reactor gasoline 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 gas reprocessing / Franz Baumgärtner, Hubert Goldacker, and Helmut Schmieder --
The separation of uranium and plutonium through electrolytic relief within the purex method / 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. provide, W.W. Morgan, K.K. Mehta, and F.P. Sargent --
advancements in thorium-uranium separation within the acid-thorex technique / 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 spinoff actinides from strength reactor fuels and creation of warmth resource isotopes / G. Koch --
Separation of actinides from purex-type excessive lively waste raffinates : improvement of experimental reviews at JRC-ISPRA institution / L. Cecille, H. Dworschak, F. Girardi, B.A. Hunt, F. Mannone, and F. Mousty --
elimination of americium and curium from high-level wastes / W.D. Bond and R.E. Leuze --
Americium restoration and purification at Rocky apartments / 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 serious evaluation / Jack L. Ryan and Lane A. Bray --
fresh Savannah River event 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 stories 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, ok. 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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8 this fractions. eluate, ted of to by w e i g h t / G . C . Q . ) . 5 close concentration L1NO3 possible actinide/lanthanide and g i v e n i n T a b l e are mediocre. for : αξ^ = is a higher it compatible (TBP 27% are couple extraction the make e l u t i o n curve s t a t i o n a r y phase obtained requires p H , to the conditions, conditions separation are adop- grouped IV. de &cpa/iatsion In column packed with a TBP 27% by wt/GCQ. mXxtxxKC stage solution fixation . 1st cycle . 8 3 cycles = scrubbing (LiN0 ) = 8 M elution ( L 1 N O 3 ) = The tion II.

A Figure 5. ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. BOURGES E T A L . 0 RECYCLIN6 WASTE Al(N0 ) 3 ε Eu ADJUSTMENT . 1 kg Ρ το W A S T E φ é * é 2 "Cm Τ TO LA TEL τπ . TO WASTE •0) *"Am TO RECYCLING * Am 3 2*3Am RECYCLING 2" Cm I f TO L. A Figure 6. ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. ch004 Figure 7. ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. 4. Transuranium BOURGES E T A L . S o l u t i o n (1) : Sulfonitric radiometry, values).

1cm I SEPARATIONS LACTIC ACID 1 M P H 3 FLOW RATE = 250 m l . 02 2 U 3 { RETENTION 1U % C m (23mg) FIG. 3 Η FIG. H ^/7//7/////Y7ZV (201 mg) : / (590 mg ) 7 y//A Eluate volume ( I ) Figure 1. Elution curves for Cm: 244 (a) first experiment; (b) second experiment. ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. ch004 BOURGES E T A L . ; ACS Symposium Series; American Chemical Society: Washington, DC, 1980. ch004 coefficients thus element to in the is III. W h i l e the resolution K])(M ) After carried of by system fixation out.

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