Generation IV Reactor Cooling by Gas-lift”Generation IV Reactor Cooling by "Gas-lift” ... There...
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Generation IV Reactor Cooling by "Gas-lift” Pavel Zitek, Jaison Chemmachery, Jiri Polansky, Vaclav Valenta University of West Bohemia in Pilsen PROPERTIES OF WATER EXPERIMENTAL DEVICE FOR RESEARCH OF SEPARATION BUBBLES Test loop Bubble generator design for gas system technology facility Bubble separator design for gas system technology facility Research of separating the gas from the liquids we have prepared a proposal for a new experimental loop. The main components are the loop generator and separator bubbles. We have already completed the initial numerical study of flow in the separator air inlet bubble generator suction air flowmeter water separator gas separator air outlet separated water outlet expansion vessel extraction equipment pump flowmeter drain valve 55 mm 5° 7, 53 mm 22,5° 128 mm 18 gas injektion holes 3,2 mm flow 128 mm 140 mm annular gas distribution channel 487 mm 125 mm Pavel Zitek, Assistant Professor [email protected] Jaison Chemmachery Student Jiri Polansky, Assoc. Prof. , Chief Scientist polansky Vaclav Valenta, Dr., Senior Expert in the Nuclear Power Department of Power System Engineering, University of West Bohemia in Pilsen, Czech Republic @kke.zcu.cz Ecole Centrale Marseille Marseille, France INTRODUCTION There is possible to use a very well known gas-lift for the intensification of natural flow in nuclear reactors. Gas-lift is replaced classic pumps with which they are currently problems in the case of high-temperature reactors. With the intensification of the natural flow are able to pay 1/2 to 4/5 the paid thermal performance when using forced air, depending on the total pressure loss of the primary circuit. It is only possible to use the continual gas delivery method in nuclear reactors. It is possible to use He as a gas. In MSR the gas-lift is suitable for cleaning the fuel-cooling mixture of fluoride salts from gaseous fission products and therefore removing the problems with „Xenon Fission product poisoning“ of classic reactors. There is applicable the bubble mode and the disperse bubble mode that allows larger flow intensification - from the types of the two-phase flow. The other modes like slug mode, churn mode and annular mode are unsuitable for non-homogeneous distribution of the phases. Flow paterns Map of distribution of the types of a two-phase flow (Taitel) Finely dispersed bubbles Bubble Churn Annular Slug 0.01 1.0 10.0 100.0 Gas Superficial Velocity, U [m/s] gs Liquid Superficial Velocity, U [m/s] ls 0.1 0.10 1.00 10.00 Bubbly Slug Churn Annular Dispersed bubble DEMONSTRATOR OF THE TWO-PHASE FLOW Two-phase flow demonstrator and its schema Exchangeable nozzle reducer The experimental device (Two-phase flow demonstrator - TFD) is a model device that is used for experimental studies of the gas-lift system and its influence on the natural convection support. The device represents a very simplified model of the primary circuit of the reactor with fuel in liquid salts. In the TFD unlike the MSR there is normal water flowing and the supplied gas is air. The measurings in water and air provide series of interesting results and points out the problems that can occur during the construction of the device with flowing liquid salts. 7 M 12 G 1/4 wall matrix M12 reduction seal removable liner conical heat exchanger PIV core area pull chimney area input gas area volume compensator 70/80 360 300 1 610 mm 200 2 160 mm 1 200 mm Numerical simulation NUMERICAL SIMULATION Mathematical model is established on the system of Navier- Stokes equations for turbulent multiphase flow of incompressible liquid and compressible gas. For turbulence model, the Reynolds stress model is adopted. Non-equilibrium wall functions are used to model the flow near the blade profiles and walls of separator. The numerical model is solved using the Runge-Kutta method in form of the finite volumes (FLUENT 14). Coupled implicit scheme with the second order accuracy and default under relaxation factors was applied. Tree-dimensional non-structured r é ù =-×+×+ = ë û 2 3 2 0,0041 2,2321 699,99 0,9986 T T kg m R [ ] = ×- ×+ × = 2 2 0,0118 7,3412 5320,2 0,9654 p c T T J kg K R [] h - - = × ×- × ×+ × = 7 2 4 2 2 10 1 10 0,0241 0,9977 T T Pa s R
Transcript of Generation IV Reactor Cooling by Gas-lift”Generation IV Reactor Cooling by "Gas-lift” ... There...
Generation IV Reactor Cooling by "Gas-lift”Pavel Zitek, Jaison Chemmachery, Jiri Polansky, Vaclav Valenta
University of West Bohemia in Pilsen
PROPERTIES OF WATER
EXPERIMENTAL DEVICE FOR RESEARCH OF SEPARATION BUBBLES
Test loop
Bubble generator design for gas system technology facility
Bubble separator design for gas system technology facility
Research of separating the gas from the liquids we have prepared a proposal for a new experimental loop. The main components are the loop generator and separator bubbles. We have already completed the initial numerical study of flow in the separator
air inlet
bubble generator
suction air
flowmeterwater separator
gas separator
air outlet
separated water outlet
expansion vessel
extraction equipment
pumpflowmeter
drain valve5
5 m
m
5°
7, 53
mm
22,5
° 12
8 m
m
18 gas injektion holes 3,2 mm
flow
12
8 m
m
14
0 m
m
annular gas distribution channel
487 mm
125 mm
Pavel Zitek, Assistant [email protected]
Jaison Chemmachery Student
Jiri Polansky, Assoc. Prof. , Chief Scientistpolansky
Vaclav Valenta, Dr., Senior Expert in the Nuclear Power
Department of Power System Engineering,University of West Bohemia in Pilsen,Czech Republic
@kke.zcu.cz Ecole Centrale MarseilleMarseille, France
INTRODUCTION
There is possible to use a very well known gas-lift for the intensification of natural flow in nuclear reactors. Gas-lift is replaced classic pumps with which they are currently problems in the case of high-temperature reactors. With the intensification of the natural flow are able to pay 1/2 to 4/5 the paid thermal performance when using forced air, depending on the total pressure loss of the primary circuit.It is only possible to use the continual gas delivery method in nuclear reactors. It is possible to use He as a gas. In MSR the gas-lift is suitable for cleaning the fuel-cooling mixture of fluoride salts from gaseous fission products and therefore removing the problems with „Xenon Fission product poisoning“ of classic reactors. There is applicable the bubble mode and the disperse bubble mode that allows larger flow intensification - from the types of the two-phase flow. The other modes like slug mode, churn mode and annular mode are unsuitable for non-homogeneous distribution of the phases.
Flow paterns
Map of distribution of the types of a two-phase flow (Taitel)
Finely dispersed bubbles
Bubble
Churn Annular
Slug
0.01
1.0 10.0 100.0
Gas Superficial Velocity, U [m/s]gs
Liq
uid
Su
pe
rfic
ial V
elo
city
, U
[m
/s]
ls
0.1
0.10
1.00
10.00
Bubbly Slug Churn Annular Dispersed bubble
DEMONSTRATOR OF THE TWO-PHASE FLOW
Two-phase flow demonstrator and its schemaExchangeable nozzle reducer
The exper imental device (Two-phase f low demonstrator - TFD) is a model device that is used for experimental studies of the gas-lift system and its influence on the natural convection support. The device represents a very simplified model of the primary circuit of the reactor with fuel in liquid salts. In the TFD unlike the MSR there is normal water flowing and the supplied gas is air. The measurings in water and air provide series of interesting results and points out the problems that can occur during the construction of the device with flowing liquid salts.
7
M 1
2
G 1
/4
wall
matrixM12 reduction
sealremovable
liner
conical
heatexchanger
PIV
corearea
pull chimneyarea
input gasarea
volumecompensator
70/80
360
30
0
1 610 mm
20
0
2 1
60
mm
1 2
00
mm
Numerical simulation
NUMERICAL SIMULATION
Mathematical model is established on the system of Navier-Stokes equations for turbulent multiphase flow of incompressible liquid and compressible gas. For turbulence model, the Reynolds stress model is adopted. Non-equilibrium wall functions are used to model the flow near the blade profiles and walls of separator. The numerical model is solved using the Runge-Kutta method in form of the finite volumes (FLUENT 14). Coupled implicit scheme with the second order accuracy and default under relaxation factors was applied. Tree-dimensional non-structured
r é ù=- ×+ ×+ =ë û2 3 20,0041 2,2321 699,99 0,9986T T kg m R
[ ]= ×- ×+ × =2 20,0118 7,3412 5320,2 0,9654pc T T J kg K R
[]h - -=× ×-× ×+ × =7 2 4 22 10 1 10 0,0241 0,9977T T Pa s R
