Subchannel analysis of nanofluids application to VVER-1000 reactor

Zarifi, Ehsan; Jahanfarnia, Gholamreza; Veysi, Farzad

doi:10.1016/j.cherd.2013.01.018

Cited by 31 publications

(14 citation statements)

References 16 publications

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“…The output are core pressure drop, distribution of enthalpy, coolant flow rate, fuel and cladding temperatures, heat flux, DNBR and heat transfer coefficient. This code has been used for several analyses such as thermal-hydraulic evaluation for AP1000 core and subchannel design [2], the influence of nozzle and spacer grid [4], radial and axial power fluctuation [5], VVER reactors [6][7][8][9][10][11][12].…”

Section: Cobra-en Codementioning

confidence: 99%

Validation of Simbat-PWR Using Standard Code of Cobra-en on Reactor Transient Condition

Isnaini

Subekti

2016

Tri Dasa Mega

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VALIDATION OF SIMBAT-PWR USING STANDARD CODE OF COBRA-EN ON REACTOR TRANSIENT CONDITION.The validation of Pressurized Water Reactor typed Nuclear Power Plant simulator developed by BATAN (SIMBAT-PWR) using standard code of COBRA-EN on reactor transient condition has been done. The development of SIMBAT-PWR has accomplished several neutronics and thermal-hydraulic calculation modules. Therefore, the validation of the simulator is needed, especially in transient reactor operation condition. The research purpose is for characterizing the thermal-hydraulic parameters of PWR1000 core, which is able to be applied or as a comparison in developing the SIMBAT-PWR. The validation involves the calculation of the thermal-hydraulic parameters using COBRA-EN code. Furthermore, the calculation schemes are based on COBRA-EN with fixed material properties and dynamic properties that are calculated by MATPRO sub routine (COBRA-EN+MATPRO) for reactor condition of startup, power rise and power fluctuation from nominal to over power. The comparison of the temperature distribution at nominal 100% power shows that the fuel centerline temperature calculated by SIMBAT-PWR has 8.76% higher than COBRA-EN and 7.70% lower than COBRA-EN+MATPRO. In general, SIMBAT-PWR calculation results on fuel temperature distribution are mostly between COBRA-EN and COBRA-EN+MATPRO results. The deviations of the fuel centerline, fuel surface, inner and outer cladding as well as coolant bulk temperature in the SIMBAT-PWR and the COBRA-EN calculation, are due to the difference of the gap between heat transfer coefficient and the cladding thermal conductivity.Keywords: transient, thermal-hydraulics, PWR, simulator, COBRA-EN, MATPRO. ABSTRAK VALIDASI SIMBAT-PWR MENGGUNAKAN KODE STANDAR COBRA-EN DALAM KONDISI REAKTOR TRANSIEN. Telah dilakukan validasi Simulator Pembangkit Listrik Tenaga Nuklir tipe Pressurized Water Reactor yang dikembangkan oleh BATAN (SIMBAT-PWR

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Section: Cobra-en Codementioning

confidence: 99%

Validation of Simbat-PWR Using Standard Code of Cobra-en on Reactor Transient Condition

Isnaini

Subekti

2016

Tri Dasa Mega

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“…Commonly used nanoparticles, such as metal oxide, significantly enhance the thermal properties of the carrier fluids. Nanofluids may be used in hybrid powered machines, transformer oil, motor cooling, solar water heating and nuclear reactor, refrigeration, microscale mixers, coolants and waste heat boiler systems as noted by Minkowycz et al [1], Zarifi et al [2], Gravel et al [3] and Nield and Bejan [4]. The concept of nanofluids was popularized by Choi in 1995 [5].…”

Section: Introductionmentioning

confidence: 99%

Numerical investigation of Von Karman swirling bioconvective nanofluid transport from a rotating disk in a porous medium with Stefan blowing and anisotropic slip effects

Bég¹,

Kabir

Uddin

et al. 2020

Proceedings of the Institution of Mechanical Engineers, Part C:

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In recent years, significant progress has been made in modern micro- and nanotechnologies for micro/nano-electronic devices. These technologies are increasingly utilizing sophisticated fluid media to enhance performance. Among the new trends is the simultaneous adoption of nanofluids and biological micro-organisms. Motivated by bio-nanofluid rotating disk oxygenators in medical engineering, in the current work, a mathematical model is developed for steady convective von-Karman swirling flow from an impermeable radially stretched disk rotating in a Darcy porous medium saturated with nanofluid doped with gyrotactic micro-organisms. Anisotropic slip at the wall and blowing effects due to concentration are incorporated. The nano-bio transport model is formulated using nonlinear partial differential equations, which are transformed to a set of similarity ordinary differential equations (SODEs) by appropriate transformations. The transformed boundary value problem is solved by a Chebyshev spectral collocation method (CSCM). Impacts of key parameters on dimensionless velocity components, concentration, temperature and motile microorganism density distributions are investigated and graphically visualized. Validation with previous studies is included. It is found that that the effects of suction provide a better enhancement of the heat, mass and microorganisms transfer in comparison to blowing. Moreover, physical quantities decrease with higher slip parameters irrespective of the existence of blowing. Temperature is suppressed with increasing thermal slip, while nanoparticle concentration is suppressed with increasing wall mass slip. Micro-organism density number increases with the greater microorganism slip. Radial skin friction is boosted with positive values of the power law stretching parameter, whereas it is decreased with negative values. The converse response is computed for circumferential skin friction, nanoparticle mass transfer rate and motile micro-organism density number gradient. Results from this study are relevant to novel bioreactors, membrane oxygenators, food processing and bio-chromatography.

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“…o C [3][4][5]. COBRA-EN code is also used on capability enhancement for VVER reactor calculation [2], deterministic optimum loading pattern [6], thermal-hydraulics modeling of nanofluids [7], sub-channel analysis of nano fluid [8] and other research in VVER-1000 reactor [9][10][11].…”

Section: Introductionmentioning

confidence: 99%

A Comparison in Thermal-Hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity

Isnaini

Mutiara

2016

Jurnal Pengembangan Energi Nuklir

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A COMPARISON IN THERMAL-HYDRAULICS ANALYSIS OF PWR-1000 USING FIXEDAND TEMPERATURE FUNCTION OF THERMAL CONDUCTIVITY. A study to analyze theinfluence of the fuel-cladding’s thermal conductivity on the sub-channel of pressurized waterreactor 1000 (PWR-1000) using COBRA-EN computer code was conducted. The purpose ofthis research is to gain complete understanding of sub-channel thermal-hydraulic aspectsrelated to fuel performance, especially the appropriate range of thermal conductivity of UO2fuel (kf) and zircaloy-4 cladding (kc) in order to obtain an accurate sub-channel analysisrelated to its safety behavior. The research was conducted by comparing the calculation withthe combination values of the fixed kf and kc, as well as the calculation using kf and kc astemperature function. The fixed kf using in this calculation were 5.26 W/m.K, 3.85 W/m.K,3.60 W/m.K, 3.18 W/m.K, 2.90 W/m.K, 2.53 W/m.K and 2.34 W/m.K, while the kc were13.0 W/m.K, 15.57 W/m.K, 16.75 W/m.K, 17.94 W/m.K and 18.69 W/m.K. The maximumfuel center linet emperature using kf and kca s temperature function (MATPRO) for hot sub -channel was 1717.65°C and taken as the reference in accepting the calculation result usingfixed thermal conductivity. The analysis was accepted, if the deviation between bothtemperature was in the range of -10% to 10%. This analysis results for hot sub-chan nelwas accepted for the calculation using value of kf in the range of 3.18 - 2.90 W/m.K for allall variation value of kcW. hile the calculation using value of koff 2.53 W/m.K was accepet dfor value of kc in the range of 16.76 - 18.69 W/m.K

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Subchannel analysis of nanofluids application to VVER-1000 reactor

Cited by 31 publications

References 16 publications

Validation of Simbat-PWR Using Standard Code of Cobra-en on Reactor Transient Condition

Validation of Simbat-PWR Using Standard Code of Cobra-en on Reactor Transient Condition

Numerical investigation of Von Karman swirling bioconvective nanofluid transport from a rotating disk in a porous medium with Stefan blowing and anisotropic slip effects

A Comparison in Thermal-Hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity

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