1
|
Kianpour R, Ansarifar GR. Optimization of the TiO2 nanofluid as a coolant in the VVER-1000 nuclear reactor based on the thermal reactivity feedback coefficients via the genetic algorithm. KERNTECHNIK 2021. [DOI: 10.1515/kern-2021-0010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
The purpose of this study is to display the neutronic simulation of nanofluid application to reactor core. The variations of VVER-1000 nuclear reactor primary neutronic parameters are investigated by using different volume fraction of nanofluid as coolant. The effect of using nanofluid as coolant on reactor dynamical parameters which play an important role in the dynamical analysis of the reactor and safety core is calculated. In this paper coolant and fuel temperature reactivity coefficients in a VVER-1000 nuclear reactor with nanofluid as a coolant are calculated by using various volume fractions and different sizes of TiO2 (Titania) nanoparticle. For do this, firstly the equivalent cell of the hexagonal fuel rod and the surrounding coolant nanofluid is simulated. Then the thermal hydraulic calculations are performed at different volume fractions and sizes of the nanoparticle. Then, using WIMS and CITATION codes, the reactor core is simulated and the effect of coolant and fuel temperature changes on the effective multiplication factor is calculated.
For doing optimization, an artificial neural network is trained in MATLAB using the observed data. The different sizes and various volume fractions are inputs, fuel and coolant temperature reactivity coefficients are outputs. The optimal size and volume fraction is determined using the neural network by implementing the genetic algorithms. In the optimization, volume fraction of 7% and size 77 nm are optimal values.
Collapse
Affiliation(s)
- R. Kianpour
- Department of Nuclear Engineering Faculty of Physics University of Isfahan Isfahan Iran
| | - G. R. Ansarifar
- Department of Nuclear Engineering Faculty of Physics University of Isfahan Isfahan Iran
| |
Collapse
|
2
|
Kianpour R, Ansarifar G. 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. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.07.002] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
|
3
|
|
4
|
Kheradmand Saadi M, Shahriari M, Zolfaghari A. Xenon transient simulation of the VVER-1000 nuclear reactor using adiabatic approximation. ANN NUCL ENERGY 2010. [DOI: 10.1016/j.anucene.2010.01.005] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
|
5
|
Ahmed R, Aslam, Ahmad N, Khan MJ, Tanvir M. Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors. PROGRESS IN NUCLEAR ENERGY 2007. [DOI: 10.1016/j.pnucene.2006.12.002] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
|
6
|
Faghihi F, Fadaie A, Sayareh R. Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes. PROGRESS IN NUCLEAR ENERGY 2007. [DOI: 10.1016/j.pnucene.2006.09.003] [Citation(s) in RCA: 32] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
|
7
|
Ahmad SI, Ahmad N. Plutonium build-up credits for a material test research reactor and influence of cross-section differences on actinide production. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2006.03.013] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
|
8
|
Ahmad SUI, Ahmad N. Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor. PROGRESS IN NUCLEAR ENERGY 2006. [DOI: 10.1016/j.pnucene.2006.03.001] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
|