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Zarifi E, Jahanfarnia G, Sepanloo K. Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor. KERNTECHNIK 2022. [DOI: 10.3139/124.110625] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
This study is aimed to perform the coupled thermal-hydraulic/neutronic analysis of nanofluids as the coolant in the hot fuel assembly of VVER-1000 reactor core. Water-based nanofluid containing various volume fractions of Al2O3 nanoparticle is analyzed. WIMS and CITATION codes are used for neutronic simulation of the reactor core, calculating neutron flux and thermal power distribution. In the thermal-hydraulic modeling, the porous media approach is used to analyze the thermal behavior of the reactor core and the subchannel analysis is used to calculate the hottest fuel assembly thermal-hydraulic parameters. The derived conservation equations for coolant and conduction heat transfer equation for fuel and clad are discretized by Finite volume method and solved numerically using visual FORTRAN program. Finally the analysis results for nanofluids and pure water are compared together. The achieved results show that at low concentration (0.1 percent volume fraction) alumina is the optimum nanoparticles for normal reactor operation.
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Affiliation(s)
- E. Zarifi
- Reactor and nuclear safety school Nuclear Science and Technology Research Institute (NSTRI) 4155-1339 , Tehran Iran
| | - G. Jahanfarnia
- Department of Nuclear Engineering, Science and Research Branch Islamic Azad University 14515-775 , Tehran Iran
| | - K. Sepanloo
- Reactor and nuclear safety school Nuclear Science and Technology Research Institute (NSTRI) 4155-1339 , Tehran Iran
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Salehi D, Jahanfarnia G, Zarifi E. Thermal-hydraulic analysis of Al2O3 nanofluid as a coolant in Canadian supercritical water reactor by porous media approach. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110825] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Bafrani HA, Noori-kalkhoran O, Gei M, Ahangari R, Mirzaee MM. On the use of boundary conditions and thermophysical properties of nanoparticles for application of nanofluids as coolant in nuclear power plants; a numerical study. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103417] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Optimization of the fuel rod's arrangement cooled by turbulent nanofluids flow in pressurized water reactor (PWR). Chin J Chem Eng 2017. [DOI: 10.1016/j.cjche.2016.10.022] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Faghihi F, Mirvakili S, Safaei S, Bagheri S. Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.10.020] [Citation(s) in RCA: 19] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Abstract
AbstractThe main objective of this study is to predict the thermal hydraulic behavior of nanofluids as the coolant in the fuel assembly of variable moderation high performance light water reactor (VMHWR). VMHWR is the new version of high performance light water reactor (HPLWR) conceptual design. Light water reactors at supercritical pressure (VMHWR, HPLWR), being currently under design, are the new generation of nuclear reactors. Water-based nanofluids containing various volume fractions of Al2O3 nanoparticles are analyzed. The conservation equations and conduction heat transfer equation for fuel and clad have been derived and discretized by the finite volume method. The transfer of mass, momentum and energy between adjacent subchannels are split into diversion crossflow and turbulent mixing components. The governed non linear algebraic equations are solved by using analytical iteration methods. Finally the nanofluid analysis results are compared with the pure water results.
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Affiliation(s)
- E. Zarifi
- 1Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), 14155-1339, Tehran, Iran
| | - S. Tashakor
- 1Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), 14155-1339, Tehran, Iran
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