Plutonium partitioning in the Purex process with hydrazine-stabilized hydroxylamine nitrate

Richardson, G.L.; Swanson, J.L.

doi:10.2172/4173805

Cited by 38 publications

(16 citation statements)

References 2 publications

(2 reference statements)

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“…Extraction of uranium(VI), plutonium(IV), zirconium, technicium, ruthenium, neptunium, nitric and nitrous acid from a nitric acid solution into a 30% v/v TBP/paraffinic diluent mixture is predicted. Distribution coefficients, mass transfer coefficients and pressure drop are estimated as suggested by the literature (Richardson and Swanson, 1975;Groenier, 1972;Asakura et al, 2005;Hongyan et al, 2017;Kumar and Koganti, 2001;Natarajan et al, 2012;Kashid and Agar, 2007;Kashid et al, 2010). Redox reactions between the three oxidation states of Np in nitric acid solutions have been included in agreement with the literature (Birkett et al, 2007;Hongyan et al, 2017;Tachimori, 1994).…”

Section: Introductionmentioning

confidence: 65%

“…TBP can also extract a significant amount of HNO 3 , according to Richardson and Swanson (1975) and Groenier (1972):…”

Section: Mathematical Modelmentioning

confidence: 99%

“…For the prediction of distribution coefficients of U(VI), Pu(IV) and HNO 3 , Richardson's correlations have been used (Richardson and Swanson, 1975). These correlations take into account uranium, plutonium and TBP concentrations, as well as ionic strength and temperature.…”

Section: Mathematical Modelmentioning

confidence: 99%

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Mathematical Modelling of Intensified Extraction for Spent Nuclear Fuel Reprocessing

Bascone

Angeli

Fraga

2017

Computer Aided Chemical Engineering

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Small scale extractors seem to be a promising intensified alternative to the conventional solvent extraction technologies, because of the well described hydrodynamics, enhanced mass transfer, and good phase separation at the end. One of the most interesting applications of intensified extractions is the reprocessing of spent nuclear fuel. Operating in small channels can reduce the volumes of involved hazardous materials and the residence times, thus minimising the degradation of the solvent and its regeneration cost. Finally, nuclear criticality safety may be easily achieved. In this paper, the application of small channels on spent nuclear fuel reprocessing has been investigated. A mathematical model of a multi-component liquid-liquid extraction has been developed. The multi-component system consists of U, Pu, HNO 3 , HNO 2 , Zr, Ru, Tc, Np(IV), Np(V) and Np(VI), the organic solvent is a mixture of 30% (v/v) Tri-Butyl Phosphate (TBP) and a paraffinic diluent. A segmented flow pattern, with the aqueous phase dispersed in a continuous organic phase, has been assumed. Calculations for the estimation of mass transfer, redox reactions, pressure drop, nuclear criticality and TBP hydrolysis have been included in the model. To increase the flow rates, the number of small channels was increased (scale out) and a comb-like manifold was considered to ensure good flow distribution in each channel. The problem is formulated as a mixed integer nonlinear programming problem and is implemented in the General Algebraic Modeling System (GAMS). The results show that this alternative technology for liquid-liquid extraction offers advantages, especially in terms of solvent degradation and low holdup volume. 4 3 3 4 (2) The reactions may be carried out in pulsed columns, mixer-settlers or centrifugal extractors. These technologies, however, have drawbacks including the need for large amounts of head space for pulsed columns, large floor space and poor geometry for criticality control for mixersettlers. Also, long solvent residence times are necessary, leading to solvent degradation. Centrifugal contactors are the most promising as a result of the short residence time and low holdup volume. However, their use is limited in industry since they are the least reliable of the three technologies, because of their poor tolerance to solids and need of periodic replacement of the motor and the rotor (Law and Todd, 2008). Volume and solvent residence times may be significantly reduced if small scale extractors are used instead of columns and mixer settlers. The large surface area to volume ratio of small scale extractors can also address criticality issues. There are no moving parts and their diameter may be large enough to avoid occlusion; therefore, they can sufficiently

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Section: Introductionmentioning

confidence: 65%

“…TBP can also extract a significant amount of HNO 3 , according to Richardson and Swanson (1975) and Groenier (1972):…”

Section: Mathematical Modelmentioning

confidence: 99%

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Mathematical Modelling of Intensified Extraction for Spent Nuclear Fuel Reprocessing

Bascone

Angeli

Fraga

2017

Computer Aided Chemical Engineering

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“…Here, the well-known correlating equations of the equilibrium distribution ratios in SEPHIS [10][11][12] have been adopted for the three codes, except EXTRA-M. These correlations are expressed using the NO 3 À concentration in solute-free molal units.…”

Section: Computer Programs and Flowsheet Conditions 1 Numericalmentioning

confidence: 99%

Effect of the Major Parameters on Pu Accumulation Predicted Using Several Numerical Codes for PUREX Solvent Extraction Process

Nabeshima¹

2011

Journal of Nuclear Science and Technology

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The abnormal accumulation of Pu(IV) in the first co-decontamination process has been studied under a hypothetical flowsheet using computer simulation programs, i.e., MIXSET-X, EXTRA-M, ESSCAR, and SAFE, to understand the program characteristics and the effects of the major independent parameters incorporated in the codes. The characteristic quantities on the Pu(IV) accumulation, e.g., the peak concentrations of Pu(IV) in the first HA extractor and the corresponding values of the independent variables, have been demonstrated to be good indicators for comparing quantitatively among the numerical predictions made using different codes. The effects of the basic models adopted for the numerical codes and the effects of the equilibrium distribution ratio have been demonstrated and discussed. Moreover, the strong effects of the flowsheet parameters, i.e., the flow rates and the solute concentrations of the external feeds, as well as the extractor length have also been examined.

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“…The original, SEPHIS-MOD1, was written specifically to provide a model for predicting time-dependent behavior of the PUREX solvent extraction process (Groenier 1972). Improvements were made to the program as SEPHIS-MOD2 and MOD3 wherein the rigor of the algorithms used for equilibrium distribution calculations were enhanced with better correlation factors and provisions for handling salting effects of inextractable species and plutonium reduction (Richardson 1973, Richardson 1975, Watson, 1975. The work in SEPHIS-MOD4 again resulted in several improvements to previous versions.…”

Section: Sephis Codementioning

confidence: 99%

Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing

Tranter¹,

Haefner²

2008

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Plutonium partitioning in the Purex process with hydrazine-stabilized hydroxylamine nitrate

Cited by 38 publications

References 2 publications

Mathematical Modelling of Intensified Extraction for Spent Nuclear Fuel Reprocessing

Mathematical Modelling of Intensified Extraction for Spent Nuclear Fuel Reprocessing

Effect of the Major Parameters on Pu Accumulation Predicted Using Several Numerical Codes for PUREX Solvent Extraction Process

Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing

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