Extraction of Am(III) by benzyldibutylamine from nitrate solutions of lanthanides

1981 ◽  
Vol 46 (1) ◽  
pp. 194-200 ◽  
Author(s):  
Marta Vojtíšková ◽  
Věra Jedináková ◽  
Libor Kuča
Keyword(s):  
Nitric Acid ◽  
Nuclear Fuel ◽  
Organic Phase ◽  
Spent Nuclear Fuel ◽  
Optimum Conditions ◽  
Separation Factors ◽  
Nitrate Solutions

Benzyldibutylamine is a suitable extractant for the separation of Am(III) and Ln(III) from the acidic nitrate solutions. The effect of lanthanides and yttrium on the extraction of Am(III) has been followed under the conditions modelling the content of these components in the spent nuclear fuel. The separation factors αAm/Ln were evaluated for the optimum conditions found for the separation of Am(III) from the lanthanides. The coextraction of nitric acid and water into the organic phase is discussed.

Extraction of americium with benzyldibutylamine from nitrate solutions

1979 ◽  
Vol 44 (8) ◽  
pp. 2366-2372 ◽  
Author(s):  
Věra Jedináková ◽  
Jana Cibulková ◽  
Libor Kuča
Keyword(s):  
Nitric Acid ◽  
Chemical Analysis ◽  
Ir Spectra ◽  
Aqueous Phase ◽  
Organic Phase ◽  
Nuclear Fission ◽  
Salting Out ◽  
Nitrate Medium ◽  
Separation Factors ◽  
Nitrate Solutions

The extraction of Am(III) with benzyldibutylamine from nitrate medium was examined in dependence on the concentration of nitric acid, kind and concentration of the salting-out agent in the aqueous phase, and on the solvent. Am(III) is extracted into the organic phase in the form of {(R3NH+)α, Am(NO3)52-}. The IR spectra of the organic phase are discussed and confronted with the results of the chemical analysis of the organic phase. The extraction of Am(III) and of lanthanoids was found to be considerably higher than that of some products of corrosion and nuclear fission (Cs, Sr, Zr, Fe), which is documented by the high values of the separation factors.

Calculation and Optimization of Plasma Utilization Process of Inflammable Wastes after Spent Nuclear Fuel Recycling

2014 ◽  
Vol 1040 ◽  
pp. 433-436 ◽  
Author(s):  
A.G. Karengin ◽  
A.A. Karengin ◽  
I.Yu. Novoselov ◽  
N.V. Tundeshev
Keyword(s):  
Nitric Acid ◽  
Acid Solution ◽  
Nuclear Fuel ◽  
Nitric Acid Solution ◽  
Mass Fraction ◽  
Spent Nuclear Fuel ◽  
Air Plasma ◽  
Practical Application

There are shown modeling results of the joint utilization process of tributylphosphate’s spent solutions into hexachlorinebutadiene for uranium and plutonium extraction from nitric acid solution of spent nuclear fuel and its recycling wastes. Utilization process was carried out for widely temperature and mass fraction ranges of air plasma coolant. Also optimal consist of inflammable water-organic compositions and modes for practical application this process in air plasma was determined.

The influence of dibutylphosphate on actinide extraction by 30% tributylphosphate

2000 ◽  
Vol 88 (5) ◽  
Author(s):  
I. May ◽  
Robin J. Taylor ◽  
A.L. Wallwork ◽  
J.J. Hastings ◽  
Yu.S. Fedorov ◽  
...  
Keyword(s):  
Nitric Acid ◽  
Nuclear Fuel ◽  
Organic Phase ◽  
Successful Operation ◽  
Careful Control ◽  
Nuclear Fuel Reprocessing ◽  
Actinide Extraction ◽  
Fuel Reprocessing ◽  
Nitrate Complexes

The careful control of actinide distribution between 30% tributylphosphate (TBP) in organic diluent and nitric acid is vital to the successful operation of nuclear fuel reprocessing plants. Uranium (VI) and tetravalent actinides are extracted into the organic phase as the nitrate complexes UO

scholarly journals Pulse radiolysis study on the reactivity of NO3˙ radical toward uranous(iv), hydrazinium nitrate and hydroxyl ammonium nitrate at room temperature and at 45 °C

2020 ◽  
Vol 22 (9) ◽  
pp. 5188-5197 ◽  
Author(s):  
R. Musat ◽  
J. L. Marignier ◽  
C. Le Naour ◽  
S. Denisov ◽  
L. Venault ◽  
...  
Keyword(s):  
Nitric Acid ◽  
Ammonium Nitrate ◽  
Nuclear Fuel ◽  
Pulse Radiolysis ◽  
Room Temperature ◽  
Spent Nuclear Fuel ◽  
Acid Solutions ◽  
Nitric Acid Solutions ◽  
No3 Radical

Concentrated nitric acid solutions subjected to radiation produce radicals of extreme importance in the reprocessing of spent nuclear fuel.

Capture of iodine and organic iodides using silica zeolites and the semiconductor behaviour of iodine in a silica zeolite

2016 ◽  
Vol 9 (3) ◽  
pp. 1050-1062 ◽  
Author(s):  
Tung Cao Thanh Pham ◽  
Son Docao ◽  
In Chul Hwang ◽  
Mee Kyung Song ◽  
Do Young Choi ◽  
...  
Keyword(s):  
Nitric Acid ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Gas Mixture ◽  
Fuel Rods ◽  
Nuclear Fuel Rods ◽  
Zeolite P ◽  
Radioactive Species

During the reprocessing of spent nuclear fuel rods, a highly moist off-gas mixture containing various volatile radioactive species, such as iodine (I2), organic iodides and nitric acid, is produced.

Calculation and Optimization of Plasma-Based Utilization Process of Inflammable Wastes after Reprocessing of Spent Nuclear Fuel of Closed Nuclear Cycle

2015 ◽  
Vol 1084 ◽  
pp. 178-182 ◽  
Author(s):  
Alexander Karengin ◽  
Alexey Karengin ◽  
Ivan Novoselov ◽  
Nikolay Tundeshev
Keyword(s):  
Nitric Acid ◽  
Acid Solution ◽  
Nuclear Fuel ◽  
Nitric Acid Solution ◽  
Spent Nuclear Fuel ◽  
Practical Implementation ◽  
Air Plasma ◽  
Wide Range ◽  
Mass Fractions ◽  
Processing Wastes

This work demonstrates the results of modeling the joint utilization process of the spent solutions of tributylphosphate with hexachlorinebutadiene for extracting uranium and plutonium from a nitric acid solution of spent nuclear fuel and its processing wastes. Calculations are made for a wide range of temperature and mass fractions of air plasma coolant. Also, optimal inflammable water-organic compositions and work regimes for the practical implementation of this process in air plasma were determined.

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