Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Comparative investigation of temperature reactivity feedback coefficients in a pressurized water reactor (PWR) with Alumina (Al2O3) and Titania (TiO2) nano-fluids as coolant

Document Type : Scientific Note

Authors

R. Kianpour
G.R. Ansarifar

Faculty of Physics, University of Isfahan, P.O.Box: 81746-73441, Isfahan-Iran

https://doi.org/10.24200/nst.2021.1304
Abstract
In the present work, using different volume percentages and different sizes of TiO2 (Titania) and Al2O3 (Alumina) nanoparticles, the important and essential parameters of VVER-1000 reactor, including dynamic parameters of the reactor (such as temperature reactivity coefficients) that play an important role in reactor dynamic analysis and core safety requirements are calculated. For this purpose, at first the equivalent cell of the fuel rod and the surrounding coolant nanofluid in the hexagonal fuel cell of the VVER-1000 reactor is determined. After that, thermohydraulic calculations are performed using the ANSYS FLUENT simulator software in different concentrations and sizes of nanoparticles to study their effect on the heat transfer coefficient, fuel, and coolant temperature parameters. Then, using WIMS and CITATION neutron computing codes, the reactor core is simulated. The effect of coolant nanofluid and fuel temperature changes on the effective multiplication factor is calculated and analyzed. The fuel and coolant temperature reactivity coefficients are determined. These coefficients are calculated by varying the concentration and size of nanoparticles in the coolant

Highlights

1. S. Khanjani, et al, Effect of cut twisted tape and Al2O3 nanofluid on heat transfer of double tube heat exchanger, Modares Mechanical Engineering, 15 (11), 181-190(2015).

 

2.             H. Aslani, M. Moghiman, Experimental investigation and fuzzy logic modelling of nanofluid solidification behavior, Modares Mechanical Engineering, 15 (11), 284-292 (2016).

 

3.             S.U.S. Choi, Enhancing thermal conductivity of fluids with nanoparticles, In developments and applications of non-newtonian flows, ASME Fluids Engineering Division (FED), 66, 99- 103 (1995).

 

4.             S. Tashakor, et al, Neutronic analysis of HPLWR fuel assembly cluster, Annals of Nuclear Energy, 50, 38-43 (2012).

 

5.             J. Buongiorno, et al, Nanofluids for enhanced economics and safety of nuclear reactors: an evaluation of the potential features, issues, and research gaps, Nuclear Technology, 162 (1), 80-91 (2008).

 

6. F. Salimi, J. Salimi, A review of nanofluid applications in the field of heat transfer and mass transfer Scientific-Extension Quarterly , New Process, 42, (1392).

 

7. S.U.I. Ahmad, N.A. Aslam, Effect of different cross-section data sets on reflectors of a typical material test research reactor, Prog. Nucl. Energy, 48(2), 155-164 (2006).

 

8.             R. Kianpour, G.R. Ansarifar, Assessment of the nano-fluid effects on the thermal reactivity feedback coefficients in the VVER-1000 nuclear reactor with nano-fluid as a coolant using thermal hydraulic and neutronics analysis, Annals of Nuclear Energy, 133, 623-636 (2019).

 

9.             Y. Xuan, W. Roetzel, Conceptions for heat transfer correlation of nanofluids. International Journal of heat and Mass transfer, 43, 3701-3707 (2000).

 

10.          M.H. Kayhani, et al, Experimental study of convective heat transfer and pressure drop of TiO2/water nanofluid. International Communications in Heat and Mass Transfer, 39 (3), 456-462 (2012).

 

11.          C.H. Chon, et al, Empirical correlation finding the role of temperature and particle size for nanofluid (Al2O3) thermal conductivity enhancement. Applied Physics Letters, 87 (15), 153107 (2005).

 

12.          Bushehr, VVER-1000 reactor, Final Safety Analysis Report (FSAR), Chapter 4, Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow, (2003).

 

13. R. Kianpour, G.R. Ansarifar, M. Fathi, Optimal Design of a VVER-1000 Nuclear Reactor Core with Dual Cooled Annular Fuel based on the Reactivity Temperature Coefficients using Thermal hydraulic and Neutronic Analysis by implementing the Genetic Algorithms, Annals of Nuclear Energy, 148, 107682 (2020).

 

14.          N.E. Todreas, M.S. Kazimi, Nuclear systems: thermal hydraulic fundamentals, CRC Press, (2011).

 

15.          J.R. Lamarsh, Introduction to nuclear reactor theory, Addison-Wesley Reading, MA, (1966).

 

16. A. Koraniani, Optimal fuel richness design of Bushehr nuclear reactor based on thermohydraulic parameters and maximum radial power factor, Master Thesis, University of Isfahan, (1398).

 

17. D.L. Hetrick, Dynamics of Nuclear Reactors the University of Chicago Press Chicago and London, (1971).

Keywords

Pressurized water reactor (PWR)
Nano fluid
Temperature reactivity coefficients
Neutronics analysis
Thermal hydraulic analysis
Heat transfer coefficient
1. S. Khanjani, et al, Effect of cut twisted tape and Al2O3 nanofluid on heat transfer of double tube heat exchanger, Modares Mechanical Engineering, 15 (11), 181-190(2015).
 
2.             H. Aslani, M. Moghiman, Experimental investigation and fuzzy logic modelling of nanofluid solidification behavior, Modares Mechanical Engineering, 15 (11), 284-292 (2016).
 
3.             S.U.S. Choi, Enhancing thermal conductivity of fluids with nanoparticles, In developments and applications of non-newtonian flows, ASME Fluids Engineering Division (FED), 66, 99- 103 (1995).
 
4.             S. Tashakor, et al, Neutronic analysis of HPLWR fuel assembly cluster, Annals of Nuclear Energy, 50, 38-43 (2012).
 
5.             J. Buongiorno, et al, Nanofluids for enhanced economics and safety of nuclear reactors: an evaluation of the potential features, issues, and research gaps, Nuclear Technology, 162 (1), 80-91 (2008).
 
6. F. Salimi, J. Salimi, A review of nanofluid applications in the field of heat transfer and mass transfer Scientific-Extension Quarterly , New Process, 42, (1392).
 
7. S.U.I. Ahmad, N.A. Aslam, Effect of different cross-section data sets on reflectors of a typical material test research reactor, Prog. Nucl. Energy, 48(2), 155-164 (2006).
 
8.             R. Kianpour, G.R. Ansarifar, Assessment of the nano-fluid effects on the thermal reactivity feedback coefficients in the VVER-1000 nuclear reactor with nano-fluid as a coolant using thermal hydraulic and neutronics analysis, Annals of Nuclear Energy, 133, 623-636 (2019).
 
9.             Y. Xuan, W. Roetzel, Conceptions for heat transfer correlation of nanofluids. International Journal of heat and Mass transfer, 43, 3701-3707 (2000).
 
10.          M.H. Kayhani, et al, Experimental study of convective heat transfer and pressure drop of TiO2/water nanofluid. International Communications in Heat and Mass Transfer, 39 (3), 456-462 (2012).
 
11.          C.H. Chon, et al, Empirical correlation finding the role of temperature and particle size for nanofluid (Al2O3) thermal conductivity enhancement. Applied Physics Letters, 87 (15), 153107 (2005).
 
12.          Bushehr, VVER-1000 reactor, Final Safety Analysis Report (FSAR), Chapter 4, Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow, (2003).
 
13. R. Kianpour, G.R. Ansarifar, M. Fathi, Optimal Design of a VVER-1000 Nuclear Reactor Core with Dual Cooled Annular Fuel based on the Reactivity Temperature Coefficients using Thermal hydraulic and Neutronic Analysis by implementing the Genetic Algorithms, Annals of Nuclear Energy, 148, 107682 (2020).
 
14.          N.E. Todreas, M.S. Kazimi, Nuclear systems: thermal hydraulic fundamentals, CRC Press, (2011).
 
15.          J.R. Lamarsh, Introduction to nuclear reactor theory, Addison-Wesley Reading, MA, (1966).
 
16. A. Koraniani, Optimal fuel richness design of Bushehr nuclear reactor based on thermohydraulic parameters and maximum radial power factor, Master Thesis, University of Isfahan, (1398).
 
17. D.L. Hetrick, Dynamics of Nuclear Reactors the University of Chicago Press Chicago and London, (1971).

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