Actinide partitioning-A review

Solvent Extraction and Ion Exchange

Volumn 19, Issue 3, 2001, Pages 357-390

  Mathur, J N ^a   Murali, M S ^a   Nash, K L ^b  

^a BHABHA ATOMIC RESEARCH CENTRE   (India)

^b ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CHROMATOGRAPHY; HYDROMETALLURGY; ION EXCHANGE; RARE EARTH ELEMENTS; TRANSURANIUM ELEMENTS;

FISSION PRODUCT;

SOLVENT EXTRACTION;

LIQUID-LIQUID EXTRACTION; NUCLEAR ENGINEERING; SOLVENT; WASTE;

EID: 0034943006     PISSN: 07366299     EISSN: None     Source Type: Journal    
DOI: 10.1081/SEI-100103276     Document Type: Article

References (123)

1. Burning of actinides: A complementary waste management option?
2. Bidentate organophosphorus compounds as extractants-II, extraction of cerium, promethium and americium nitrates
3. Bidentate organophosphorous compounds as extractants-II, Extraction mechanism for curium(III) nitrate
4. Removal of actinides from nuclear fuel reprocessing waste solutions with bidentate organophosphorus extractants
5. The extraction of Th(IV) and U(IV) by dihexyl-N, N-diethylcarbamoylmethylphosphonate from aqueous nitrate media
6. The thermodynamics of extraction of U(IV) and Th(IV) from nitric acid by neutral phosphorus based organic compounds
7. Selected alkyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxides as extractants for Am(III) from nitric acid media
8. Actinide recovery from waste and low grade sources
9. 4 and Pd(II) by dihexyl-N,N-diethylcarbamoylmethyl phosphonate from nitric acid
10. The extraction of zirconium from nitric acid by dihexyl-N,N-diethylcarbamoylmethylphosphonate
11. Variation in the solvent extraction of bifunctional phosphorus based compounds modified by TBP
12. 3 system
13. Extraction of americium, lanthanides and some fission product elements by bidentate phosphonates
14. Waste management analysis for the nuclear fuel cycle: I actinide recovery from aqueous salt wastes
15. Removal of actinides from selected nuclear fuel reprocessing wastes
16. Extraction of Am(III) by mixture of dihexyl-N,N-diethylcarbamoylmethyl phosphonate and tributyl phosphate in benzene from nitric acid solutions
17. Extraction of Pm(III) from acidic solutions using dihexyl-N, N-diethylcarbamoylmethyl phosphonate
18. Extraction of transuranic elements with a dihexyl-N,N-diethylcarbamoylmethylphosphonate/tributylphosphate system-initial investigations
19. The extraction of Am(III) and Fe(III) by selected dihexyl-N,N-dialkylcarbamoylmethylphosphonates, phosphinates and phosphine oxides from nitrate media
20. Extraction of transplutonium elements with diphenyl(alkyl)dialkylcarbamoyl-methyl-phosphine oxides
21. Synthesis, characterization and actinide extraction behavior of bridge-modified carbamoylmethyl-phosphonates and phosphine oxides
22. The synthesis and purification of carbamoylmethylphosphine oxides
23. The spectral properties of the carbamoylmethylphosphine oxides
24. The extraction of selected transplutonium(III) and lanthanide(III) ions by dihexyl-N,N-diethylcarbamoylmethyl phosphonate from aqueous nitrate media
25. Carbamoylmethylphosphoryl derivatives as actinide extractants: Their significance in the processing and recovery of plutonium and other actinides
26. The extraction of Am(III) from nitric acid by octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide-tri-n-butyl phosphate mixture
27. Extraction of Am from nitric acid by carbamoylphosphoryl extractants: The influence of substituents on the selectivity of Am over Fe and selected fission products
28. The extraction of Eu(III) from acidic media by octyl(phenyl)-N,N-diisobutylcarbamoylmethyl-phosphine oxide
29. Extraction of neptunium and plutonium nitrates with n-octyl(phenyl))-N,N-diisobutylcarbamoylmethylphosphine oxide
30. The separation of neptunium and plutonium from nitric acid using n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide extraction and selective stripping
31. Oxidation of pentavalent neptunium by nitrous acid in CMPO-TBP-n-dodecane
32. Extraction actinides and fission products by octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide from nitric acid media
33. Activity coefficients of carbamoylmethylphosphoryl extractants in toluene
34. A slope analysis investigation of the trivalent f-series metal CMPO complexes
35. Electrochemical study on Ce(III) nitrate complex with n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide in acetonitrile
36. Numerical modeling for coextraction of Tc(VII) with U(VI) by n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide from nitric acid solution
37. Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process-preliminary development studies
38. The TRUEX process-A process for the extraction of the transuranic elements from nitric acid wastes utilizing modified PUREX solvent
39. The TRUEX process and the management of liquid TRU waste
40. The TRUEX process: A vital tool for disposal of U.S. defense nuclear waste
41. Solvent extraction in the treatment of acidic high-level liquid waste: Where do we stand?
42. TRUEX processing of plutonium analytical solutions at Argonne National Laboratory
43. Evaluation of 1-hydroxyethane-1, 1-diphosphonic acid and sodium carbonate as stripping agents for the removal of Am(III) and Pu(IV) from TRUEX process solvent
44. Initial studies of pretreatment methods for neutralized cladding removal waste (NCRW) sludge
45. Use of TRUEX process for the pretreatment of neutralized cladding removal waste (NCRW) sludge-results of a design basis experiment
46. Use of the TRUEX process for the pretreatment of neutralized cladding removal waste (NCRW) sludge-results of FY 1990 studies
47. Pretreatment of neutralized cladding removal waste (NCRW) sludge-results of FY 1991 studies
48. Pretreatment of plutonium finishing plant (PFP) sludge, report for the period October 1990-March 1992
49. Actinide recovery from radioactive liquid wastes produced by ENEA experimental fabrication and reprocessing plants by CMPO
50. Separation and recovery of transuranium elements from liquid wastes produced by the Casaccia plutonium plant
51. Partitioning of actinides and fission products in highly-active raffinate from PUREX process by mixer-settlers
52. Separation of actinides and fission products in high-level liquid wastes by the improved TRUEX process
53. Partitioning of actinides from high-level waste streams of PUREX process using mixtures of CMPO
54. Extraction and extraction chromatographic separation of minor actinides from sulphate bearing high-level waste solutions using CMPO
55. Recovery of neptunium from highly radioactive waste solutions of PUREX origin CMPO
56. Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO
57. Counter-current studies on actinide partitioning from sulphate bearing simulated high-level wastes using CMPO
58. Partitioning of actinides from simulated high level wastes arising from reprocessing of PHWR fuels: Counter-current extraction studies using CMPO
59. Separation and recovery of uranium, neptunium and plutonium from high level waste using tributylphosphate: Counter-current studies with simulated waste solution
60. Preliminary evaluation of chromatographic techniques for the separation of radionuclides from high-level radioactive waste
61. Sequential separation of actinides and lanthanides by extraction chromatography using a CMPO-TBP/XAD 7 column
62. Separation of actinide ions from radioactive waste solutions using extraction chromatography
63. Separation and recovery of plutonium from oxalate supernatant using CMPO
64. Extraction chromatographic separation and recovery of plutonium from oxalate supernatant using CMPO
65. Separation and recovery of uranium and plutonium from oxalate supernatant
66. Utilization of ferrocyanide ion for stripping of actinides and lanthanides from CMPO phase and aqueous complexing of these metal ions with ferrocyanide ion
67. Recovery of actinides extracted by TRUEX solvent from high-level waste using complexing agents I. Batch studies
68. Recovery of actinides by TRUEX solvent from high level waste using complexing agents II counter-current studies
69. Hydrolytic and radiolytic degradation of octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide and related compounds
70. Hydrolytic and radiolytic degradation of OΦD(iB)CMPO: Continuing studies
71. Degradation of TRUEX-dodecane process solvent
72. Secondary clean up of TRUEX process solvent
73. Degradation, clean-up and reusability of octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) during partitioning of minor actinides from high level waste (HLW) solutions
74. An extractant (TRPO) for the removal and recovery of actinides from high level radioactive liquid waste
75. The extraction of actinides and other constituents from highly active waste (HAW) by trialkylphosphine oxide (TRPO)
76. Recovery of neptunium, plutonium and americium from high active waste
77. Partitioning of actinides from HAW in a continuous process by means of centrifugal extractors
78. Partitioning of TRU elements from Chinese HLLW
79. Actinide partitioning by means of the TRPO process
80. Chinese experience in the removal of actinides from highly active waste by trialkylphosphine oxide extraction
81. Hot tests of the TRPO process for the removal of TRU elements from HLLW
82. A mathematical model for the extraction of americium from HLLW by 30% TRPO and its experimental verification
83. Use of a mixture of TRPO and TBP for the partitioning of actinides from high level waste solutions of PUREX origin and its comparison with CMPO and other phosphorus based extractants
84. Extraction of neptunium with di-isodecyl phosphoric acid from nitric acid solution containing hydrogen peroxide
85. Research and development on the partitioning process at JAERI
86. Trends in the separation chemistry for nuclear fuels reprocessing
87. Solvent extraction for the chemical separations of the 5-f elements
88. Malonamides as new extractants for nuclear waste solutions
89. Diamides as actinide extractants for various waste treatment
90. 4
91. Extraction by N,N,N',N'-tetraalkyl-2-alkylpropane-1,3-diamides II. U(VI) and Pu(IV)
92. Actinide extraction chemistry with the amide type extractants
93. Comparison of extraction behaviour and basicity of some substituted malonamides
94. Substituted malonamides as extractants for partitioning of actinides from nuclear waste solutions
95. Uptake of metal ions by extraction chromatography using dimethyldibutyltetradecyl-1,3-malonamide (DMDBTDMA) as the stationary phase
96. Extraction chemistry of neptunium
97. Recovery of neptunium from highly radioactive waste solutions of PUREX origin using tributyl phosphate
98. AKUFVE studies on extraction behaviour of neptunium from simulated HLW solutions by 30% TBP
99. The application of formo- and aceto-hydroxamic acids in nuclear fuel reprocessing
100. New reducing agents for neptunium(VI) and plutonium(IV)
101. The separation of neptunium and technetium in an advanced PUREX process
102. Separation chemistry for lanthanides and trivalent actinides. Chapter 121
103. Hot test of a TALSPEAK procedure for separation of actinides and lanthanides using recirculating DTPA-lactic acid solution
104. A counter-current experiment for the separation of trivalent actinides and lanthanides by the SETFICS process
105. Enhancement of the mutual separation of lanthanide elements in the solvent extraction based on the CMPO-TBP mixed solvent by using a DTPA-nitrate solution
106. The use of soft donor ligands, 4-benzoyl-2,4-dihydro-5-methyl-2-phenylpyrazol-3-thione and 4,7-diphenyl-1, 10-phenanthroline, for improved separation of trivalent americium and europium
107. Separation of americium(III) from europium(III) with tridentate heterocyclic nitrogen ligands and crystallographic studies of complexes formed by 2,2':6',2-terpyridine with the lanthanides
108. Theoretical and experimental studies of the protonated terpyridine cation. Ab initio quantum mechanical calculations and crystal structures of two different ion pairs formed between protonated terpyridine cations lanthanate(III) ions
109. Am(III)/Eu(III) separation at low pH using synergistic mixtures composed of carboxylic acids and neutral nitrogen polydentate ligands
110. Extraction of Am(III)and Eu(III) nitrates by 2,6-di(5,6-dipropyl-1,2,4-triazin-3-yl) pyridines
111. Selective extraction of Am(III) over Eu(III) by 2,6-ditriazolyl- and 2,6-ditriazinyl pyridines
112. Actinide-lanthanide group separation using sulfur and nitrogen donor extractants
113. Extraction of Am(III) and Eu(III) from nitrate solution with purified Cyanex 301
114. The separation of Am from lanthanides by purified Cyanex 301 extraction
115. Trivalent minor actinides/lanthanides separation, using organophosphinic acids