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

Investigation of the Al2O3/ Water Nano-Fluid Concentration and Size Effects on the Neutronics and Thermal-Hydraulic Parameters in the VVER-1000 Nuclear Reactor Using Artificial Neural Networks

Document Type : Scientific Note

Authors

M Rezaee
Gh. R Ansarifar
M NasriNasrabadi
Abstract
Nowadays, many researches have been done to improve the efficiency of the nuclear power plants, one of which is the use of the dual cooled annular fuel which is an internally and externally cooled annular fuel with many advantages in heat transfer characteristics. Also, some studies have suggested that the usage of the nanoparticles in a fluid as nano-fluid can provide dramatic improvements in the thermal properties of fluid. Howere, the  usage of neutronics and the thermal hydraulic codes in order to investigate the nano-fluid effects in the nuclear reactors is complex, uneconomical and time consuming. Therefore, in this paper, to investigate the nano-fluid effects on the important parameters of the VVER-1000 nuclear reactor with dual-cooled annular fuel, effects of Al2O3/ water nano-fluid concentration and size on neutronics and the thermal-hydraulic parameters in the VVER-1000 nuclear reactor are investigated using a proper Artificial Neural Network. Results show that the trained Neural Network has good convergence and accuracy in determination of the neutronics and the thermal-hydraulic parameters. Using the presented Neural Network, important reactor parameters can be determined without neutronics and the thermal hydraulic codes, thus saving time.

Highlights

[1] K.H. Han, S.H. Chang, Development of a thermal-hydraulic analysis code for annular fuel assemblies, Nuclear Engineering and Design226 (2003) 267-275.

 

[2]          Y.S. Yang, C.H. Shin, T.H. Chun, K.W. Song, Evaluation of a dual-cooled annular fuel heat split and temperature distribution, Nucl. Sci.Tech.46 (2009) 836-845.

 

[3]          M. Kazimi, P. Hejzlar, Evaluation of high power density annular fuel for Korean OPR-1000 reactor: final report, Internal Report (2010).

 

[4] S.U. Choi, Nanofluids: from vision to reality through research, Heat Transfer 131 (2009) 83-106.

 

[5] M. Assael, C.F. Chen, I. Metaxa, W. Wakeham, Thermal conductivity of suspensions of carbon nanotubes in water, Thermophysics 25 (2004) 971-985.

 

[6] S.K. Das, N. Putra, P. Thiesen, W. Roetzel, Temperature dependence of thermal conductivity enhancement for nanofluids, Heat Transfer 125 (2003) 567-574.

 

[7]          K.H. Han, K.W. Seo, D.H. Hwang, S.H. Chang, Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels, Nucl.Eng. Des. 236 (2006) 164-178.

 

[8] G. Ansarifar, M. Ebrahimian, Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel, Annals of Nuclear Energy 87 (2016) 39-47.

 

[9] K. Hadad, A. Hajizadeh, K. Jafarpour, B. Ganapol, Neutronic study of nanofluids application to VVER-1000, Ann. Nucl. Energy 37 (2010) 1447-1455.

 

[10] J. Donnelly, A user's manual for the Chalk River version of WIMS, Atomic Energy of Canada Limited, (1986).

 

[11] T. Fowler, D. Vondy, NUCLEAR REACTOR CORE ANALYSIS CODE: CITATION, Oak Ridge National Lab. Tenn (1969).

 

[12] C.H. Shin, T.H. Chun, D.S. Oh, W.K. In, Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000, Nucl. Eng. Des.243 (2012) 291-300.

 

[13]        X.Q. Wang, A.S. Mujumdar, Heat transfer characteristics of nanofluids: a review, Therm. Sci. 46 (2007) 1-19.

 

 

[14]        Y. Xuan, W. Roetzel, Conceptions for heat transfer correlation of nanofluids, Heat Mass Transfer 43 (2000) 3701-3707.

 

[15]        C.H. Chon, K.D. Kihm, S.P. Lee, S.U. Choi, Empirical correlation finding the role of temperature and particle size for nanofluid (Al2O3) thermal conductivity enhancement, Appl. Phys. Lett.87 (2005) 107-123.

 

[16]        H.A. Mintsa, G. Roy, C.T. Nguyen, D. Doucet, New temperature dependent thermal conductivity data for water-based nanofluids, Therm. Sci.48 (2009) 363-371.

 

[17]        N. Masoumi, N. Sohrabi, A. Behzadmehr, A new model for calculating the effective viscosity of nanofluids, Appl. Phys. 42 (2009) 5501-5508.

[18] M.M. El-Wakil, Powerplant technology: Tata McGraw-Hill Education (1988).

 

[19] W. Jens, P. Lottes, Analysis of heat transfer, burnout, pressure drop and density date for high-pressure water, Argonne National Lab. (1951).

 

[20]        J.R. Lamarsh, Introduction to nuclear reactor theory: Addison-Wesley Reading, MA (1966).

 

[21]        I.H. Bae, M.G. Na, Y.J. Lee, G.C. Park, Calculation of the power peaking factor in a nuclear reactor using support vector regression models, Ann. Nucl. Energy35 (2008) 2200-2205.

Keywords

Nanofluid
Annular Fuel
Nuclear Reactor
Neutronic Parameters
Thermal-Hydraulic Parameters
Artificial Neural Networks
[1] K.H. Han, S.H. Chang, Development of a thermal-hydraulic analysis code for annular fuel assemblies, Nuclear Engineering and Design226 (2003) 267-275.
 
[2]          Y.S. Yang, C.H. Shin, T.H. Chun, K.W. Song, Evaluation of a dual-cooled annular fuel heat split and temperature distribution, Nucl. Sci.Tech.46 (2009) 836-845.
 
[3]          M. Kazimi, P. Hejzlar, Evaluation of high power density annular fuel for Korean OPR-1000 reactor: final report, Internal Report (2010).
 
[4] S.U. Choi, Nanofluids: from vision to reality through research, Heat Transfer 131 (2009) 83-106.
 
[5] M. Assael, C.F. Chen, I. Metaxa, W. Wakeham, Thermal conductivity of suspensions of carbon nanotubes in water, Thermophysics 25 (2004) 971-985.
 
[6] S.K. Das, N. Putra, P. Thiesen, W. Roetzel, Temperature dependence of thermal conductivity enhancement for nanofluids, Heat Transfer 125 (2003) 567-574.
 
[7]          K.H. Han, K.W. Seo, D.H. Hwang, S.H. Chang, Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels, Nucl.Eng. Des. 236 (2006) 164-178.
 
[8] G. Ansarifar, M. Ebrahimian, Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel, Annals of Nuclear Energy 87 (2016) 39-47.
 
[9] K. Hadad, A. Hajizadeh, K. Jafarpour, B. Ganapol, Neutronic study of nanofluids application to VVER-1000, Ann. Nucl. Energy 37 (2010) 1447-1455.
 
[10] J. Donnelly, A user's manual for the Chalk River version of WIMS, Atomic Energy of Canada Limited, (1986).
 
[11] T. Fowler, D. Vondy, NUCLEAR REACTOR CORE ANALYSIS CODE: CITATION, Oak Ridge National Lab. Tenn (1969).
 
[12] C.H. Shin, T.H. Chun, D.S. Oh, W.K. In, Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000, Nucl. Eng. Des.243 (2012) 291-300.
 
[13]        X.Q. Wang, A.S. Mujumdar, Heat transfer characteristics of nanofluids: a review, Therm. Sci. 46 (2007) 1-19.
 
 
[14]        Y. Xuan, W. Roetzel, Conceptions for heat transfer correlation of nanofluids, Heat Mass Transfer 43 (2000) 3701-3707.
 
[15]        C.H. Chon, K.D. Kihm, S.P. Lee, S.U. Choi, Empirical correlation finding the role of temperature and particle size for nanofluid (Al2O3) thermal conductivity enhancement, Appl. Phys. Lett.87 (2005) 107-123.
 
[16]        H.A. Mintsa, G. Roy, C.T. Nguyen, D. Doucet, New temperature dependent thermal conductivity data for water-based nanofluids, Therm. Sci.48 (2009) 363-371.
 
[17]        N. Masoumi, N. Sohrabi, A. Behzadmehr, A new model for calculating the effective viscosity of nanofluids, Appl. Phys. 42 (2009) 5501-5508.
[18] M.M. El-Wakil, Powerplant technology: Tata McGraw-Hill Education (1988).
 
[19] W. Jens, P. Lottes, Analysis of heat transfer, burnout, pressure drop and density date for high-pressure water, Argonne National Lab. (1951).
 
[20]        J.R. Lamarsh, Introduction to nuclear reactor theory: Addison-Wesley Reading, MA (1966).
 
[21]        I.H. Bae, M.G. Na, Y.J. Lee, G.C. Park, Calculation of the power peaking factor in a nuclear reactor using support vector regression models, Ann. Nucl. Energy35 (2008) 2200-2205.

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