5-25. In this problem, we examine the process of recovering fission materials from spent nuclear fuel rods. This is usually referred to as reprocessing of the fuel to recover plutonium (Pu) and the active isotope of uranium (U235). Reprocess ing can be done by separation of the soluble isotope nitrates from a solution in nitric acid bya solvent such as a 30% solution of tributyl phosphate (TBP) in dodecane (C12H26 in which the nitrates are preferentially soluble. Industrial reprocessing of nuclear fuels is done by countercurrent operation of many liquid-liquid separation stages. These separation stages consist of well-mixed contacting tanks, where UO2 (NO3)2 is exchanged between two immiscible liquid phases, and separation tanks, where the organic and aqueous phases are separated. A schematic of a separation stage is shown in Figure 5.25a. e Two-Phase Systems & Equilibrium Stages 155 aqueous phase organic phase organic aqueous phase phase Figure 5.25a. Liquid-liquid separation stage for reprocessing In this process an aqueous solution of uranil nitrate [UO2(NO3) 2 ] is one of the feed streams to the separation stage, and the mass flow rate of the aqueous feed phase is, m 400kg/hr stream is an organic solution of tributyl phosphate (TBP) in dodecane (C12H26 ) which we assume to be a single component. The organic and inorganic phases are assumed to be immiscible, thus only the uranil nitrate is transferred from one stream to the other. The process specifications are indicated in Figure 5.25b, and for this problem it is the mass flow rates that you are asked to determine. The second feed 11 m 400 kg /hr aqueous () 0.1 (@B) = 0.9 organic 4 phase phase (a)4=0.8 A = UO2(NO3)2 B water C organic organic phase (c0A)3= 0.02 (@c2= 1.0 aqueous 3 phase (B)'3 = 0.98 Figure 5,25h. Specified
5-25. In this problem, we examine the process of recovering fission materials from spent nuclear fuel rods. This is usually referred to as reprocessing of the fuel to recover plutonium (Pu) and the active isotope of uranium (U235). Reprocess ing can be done by separation of the soluble isotope nitrates from a solution in nitric acid bya solvent such as a 30% solution of tributyl phosphate (TBP) in dodecane (C12H26 in which the nitrates are preferentially soluble. Industrial reprocessing of nuclear fuels is done by countercurrent operation of many liquid-liquid separation stages. These separation stages consist of well-mixed contacting tanks, where UO2 (NO3)2 is exchanged between two immiscible liquid phases, and separation tanks, where the organic and aqueous phases are separated. A schematic of a separation stage is shown in Figure 5.25a. e Two-Phase Systems & Equilibrium Stages 155 aqueous phase organic phase organic aqueous phase phase Figure 5.25a. Liquid-liquid separation stage for reprocessing In this process an aqueous solution of uranil nitrate [UO2(NO3) 2 ] is one of the feed streams to the separation stage, and the mass flow rate of the aqueous feed phase is, m 400kg/hr stream is an organic solution of tributyl phosphate (TBP) in dodecane (C12H26 ) which we assume to be a single component. The organic and inorganic phases are assumed to be immiscible, thus only the uranil nitrate is transferred from one stream to the other. The process specifications are indicated in Figure 5.25b, and for this problem it is the mass flow rates that you are asked to determine. The second feed 11 m 400 kg /hr aqueous () 0.1 (@B) = 0.9 organic 4 phase phase (a)4=0.8 A = UO2(NO3)2 B water C organic organic phase (c0A)3= 0.02 (@c2= 1.0 aqueous 3 phase (B)'3 = 0.98 Figure 5,25h. Specified
Introduction to Chemical Engineering Thermodynamics
8th Edition
ISBN:9781259696527
Author:J.M. Smith Termodinamica en ingenieria quimica, Hendrick C Van Ness, Michael Abbott, Mark Swihart
Publisher:J.M. Smith Termodinamica en ingenieria quimica, Hendrick C Van Ness, Michael Abbott, Mark Swihart
Chapter1: Introduction
Section: Chapter Questions
Problem 1.1P
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Transcribed Image Text:5-25. In this problem, we examine the process of recovering fission materials from spent nuclear fuel rods.
This is usually referred to as reprocessing of the fuel to recover plutonium (Pu) and the active isotope of
uranium (U235). Reprocess ing can be done by separation of the soluble isotope nitrates from a solution in
nitric acid bya solvent such as a 30% solution of tributyl phosphate (TBP) in dodecane (C12H26
in which
the nitrates are preferentially soluble. Industrial reprocessing of nuclear fuels is done by countercurrent
operation of many liquid-liquid separation stages. These separation stages consist of well-mixed contacting
tanks, where UO2 (NO3)2 is exchanged between two immiscible liquid phases, and separation tanks,
where the organic and aqueous phases are separated. A schematic of a separation stage is shown in
Figure 5.25a.
e
![Two-Phase Systems & Equilibrium Stages
155
aqueous
phase
organic
phase
organic
aqueous
phase
phase
Figure 5.25a. Liquid-liquid separation stage for reprocessing
In this process an aqueous solution of uranil nitrate [UO2(NO3) 2 ] is one of the feed streams to the
separation stage, and the mass flow rate of the aqueous feed phase is, m 400kg/hr
stream is an organic solution of tributyl phosphate (TBP) in dodecane (C12H26 ) which we assume to be a
single component. The organic and inorganic phases are assumed to be immiscible, thus only the uranil
nitrate is transferred from one stream to the other. The process specifications are indicated in Figure 5.25b,
and for this problem it is the mass flow rates that you are asked to determine.
The second feed
11
m
400 kg /hr
aqueous
() 0.1
(@B) = 0.9
organic
4
phase
phase
(a)4=0.8
A = UO2(NO3)2
B water
C organic
organic
phase
(c0A)3= 0.02
(@c2= 1.0
aqueous
3
phase
(B)'3 = 0.98
Figure 5,25h. Specified](/v2/_next/image?url=https%3A%2F%2Fcontent.bartleby.com%2Fqna-images%2Fquestion%2F43039365-0cf0-47a1-9197-a1e58c9ae570%2Fa2675751-55e4-4492-9803-31a2cb448b31%2F2owxgqa.jpeg&w=3840&q=75)
Transcribed Image Text:Two-Phase Systems & Equilibrium Stages
155
aqueous
phase
organic
phase
organic
aqueous
phase
phase
Figure 5.25a. Liquid-liquid separation stage for reprocessing
In this process an aqueous solution of uranil nitrate [UO2(NO3) 2 ] is one of the feed streams to the
separation stage, and the mass flow rate of the aqueous feed phase is, m 400kg/hr
stream is an organic solution of tributyl phosphate (TBP) in dodecane (C12H26 ) which we assume to be a
single component. The organic and inorganic phases are assumed to be immiscible, thus only the uranil
nitrate is transferred from one stream to the other. The process specifications are indicated in Figure 5.25b,
and for this problem it is the mass flow rates that you are asked to determine.
The second feed
11
m
400 kg /hr
aqueous
() 0.1
(@B) = 0.9
organic
4
phase
phase
(a)4=0.8
A = UO2(NO3)2
B water
C organic
organic
phase
(c0A)3= 0.02
(@c2= 1.0
aqueous
3
phase
(B)'3 = 0.98
Figure 5,25h. Specified
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