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Shanmugapriyan N, Jakeer S. Biomedical aspects of entropy generation on MHD flow of TiO2-Ag/blood hybrid nanofluid in a porous cylinder. Comput Methods Biomech Biomed Engin 2024; 27:1492-1509. [PMID: 37578009 DOI: 10.1080/10255842.2023.2245520] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/29/2023] [Revised: 07/14/2023] [Accepted: 08/01/2023] [Indexed: 08/15/2023]
Abstract
This study aims to analyze the heat transfer behavior of the magnetohydrodynamic blood-based Casson hybrid nanofluid in the occurrence of a non-Fourier heat flux model and linear thermal radiation over a horizontal porous stretching cylinder with potential applications in biomedical engineering. The present investigation utilised titanium dioxide and silver nanoparticles, which exhibit considerable potential in the realm of cancer therapy. Thus, there is a growing interest among biomedical engineers and clinicians in the study of entropy production as a means of quantifying energy dissipation in biological systems. Suitable self-similarity variables are employed to transform the nonlinear mathematical equations such as velocity, temperature, skin friction coefficient, and heat transfer rate, which are computed via homotopy perturbation method (HPM). HPM computations have been executed to solve the influences of various parameters such as porosity parameter ( K = 0.0 , 1.0 , 2.0 ) , Curvature parameter ( α = 0.0 , 1.0 , 3.0 , 5.0 ) , Casson parameter ( β = 0.0 , 0.5 , 1.5 ) , inertia coefficient ( Fr = 0.5 , 1.5 , 2.5 ) , thermal relaxation parameter ( δ ∗ = 0.0 , 0.5 , 1.0 ) , radiation ( Rd = 0.0 , 0.5 , 1.0 ) , Eckert number ( Ec = 0.0 , 0.1 , 0.2 ) , Brinkman number ( Br = 0.5 , 1.0 , 1.5 ) and temperature difference parameter ( α 1 = 0.0 , 0.5 , 1.0 ) . The comparison using the homotopy perturbation technique produces a more accurate and reliable consequence than the numerical method (Runge-Kutta method). The higher values of the Casson and Curvature parameters decrease the velocity profile. The temperature profile of M = 1 and M = 0 increases with improving values of the thermal relaxation parameter. Entropy generation rises to enhance Brinkman number values, whereas Bejan number exhibits the reverse influence. Improving the value of the heat source parameter declines the Nusselt number.
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Affiliation(s)
- N Shanmugapriyan
- Department of Biomedical Engineering, Chennai Institute of Technology, Chennai, India
| | - Shaik Jakeer
- Center for Computational Modeling, Chennai Institute of Technology, Chennai, India
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2
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Li T, Xiong J, Zhang T, Chai X, Liu X. Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109774] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/08/2023]
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3
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Li J, Cai J, Li X. Conceptual design and feasibility analysis of a megawatt level low enriched uranium heat pipe cooled reactor core. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109576] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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4
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Allaf M, Okamoto K, Suzuki S, Erkan N. Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses. J NUCL SCI TECHNOL 2023. [DOI: 10.1080/00223131.2022.2159560] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/13/2023]
Affiliation(s)
- Mohammad Allaf
- Nuclear Professional School, The University of Tokyo, Tokyo, Japan
| | - Koji Okamoto
- Nuclear Professional School, The University of Tokyo, Ibaraki, Japan
| | - Shunichi Suzuki
- Nuclear Engineering and Management, The University of Tokyo, Tokyo, Japan
| | - Nejdet Erkan
- Fusion Technology Facility, United Kingdom Atomic Energy Authority (UKAEA), Rotherham, UK
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5
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Prospects for additive manufacturing of nuclear fuel forms. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2022.104493] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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6
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Startup analyses of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104405] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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7
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An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR). PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104326] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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8
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Allaf M, Okamoto K, Erkan N. Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses. J NUCL SCI TECHNOL 2022. [DOI: 10.1080/00223131.2022.2098197] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/15/2022]
Affiliation(s)
- Mohammad Allaf
- Nuclear Engineering and Management Department, The University of Tokyo, Tokyo, Japan
| | - Koji Okamoto
- Nuclear Professional School, The University of Tokyo, Shirane, Ibaraki, Japan
| | - Nejdet Erkan
- Fusion Technology Facility, United Kingdom Atomic Energy Authority (UKAEA), Rotherham, UK
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9
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Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.08.012] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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10
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Wahlquist S, Hansel J, Sabharwall P, Ali A. A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications. NUCL SCI ENG 2022. [DOI: 10.1080/00295639.2022.2082230] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
Affiliation(s)
- Scott Wahlquist
- Idaho State University, Department of Nuclear Engineering, 921 South 8th Avenue, Pocatello, Idaho 83209
| | | | | | - Amir Ali
- Idaho State University, Department of Nuclear Engineering, 921 South 8th Avenue, Pocatello, Idaho 83209
- Center for Advanced Energy Studies, Idaho Falls, Idaho
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11
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A medium temperature heat pipe cooled reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109068] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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12
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Wang Z, Han R, Guo K, Wang C, Zhang D, Tian W, Qiu S, Su G. Molecular dynamics simulation of the evaporation of liquid sodium film in the presence of non-condensable gas. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109005] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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13
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Yang H, Wang C, Zhang D, Zhang J, Tian W, Qiu S, Su G. Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111754] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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14
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Seo J, Kim D, Kim H, Hassan YA. An experimental investigation on the characteristics of heat pipes with annular type composite wick structure. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111701] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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15
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Ma K, Hu P. Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108907] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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16
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Li N, Pan LM, Wang L, Huang Y, Yuan DW. Molecular Dynamics Study on the Wettability of the Lithium Droplet and Tungsten Surface. LANGMUIR : THE ACS JOURNAL OF SURFACES AND COLLOIDS 2022; 38:2502-2514. [PMID: 35175776 DOI: 10.1021/acs.langmuir.1c02964] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/14/2023]
Abstract
In this paper, molecular dynamics (MD) simulation was used to study the wettability of lithium and tungsten. The surface energy barrier and evaporation control the static contact angle with increasing temperature. The effects of 4 different sizes of droplets and 10 different tungsten sections were evaluated. Moreover, it was found that the different arrangements of atoms on the solid surface will affect the wettability, but the size of the droplet has little effect. In addition, the situation of the droplets driven by six different external forces was evaluated. When the force increases, the two states of the droplet and stream will have different properties. Finally, we studied the phase behavior between lithium and tungsten. For example, lithium overflows from the tungsten plate. The tungsten phase is separated in the lithium plate. Lithium is faster than tungsten when it aggregates in the gas phase, and wettability will drive the effects of engulfing and spitting.
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Affiliation(s)
- Nan Li
- Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Chongqing University, Ministry of Education, Chongqing 400044, China
- School of Future Technology, University of Chinese Academy of Sciences, Beijing 100049, China
| | - Liang-Ming Pan
- Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Chongqing University, Ministry of Education, Chongqing 400044, China
| | - Lin Wang
- Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Chongqing University, Ministry of Education, Chongqing 400044, China
| | - Yanping Huang
- Nuclear Reactor Thermal Hydraulic Technology Key Laboratory, Nuclear Power Institute of China, Chengdu 610041, China
| | - De-Wen Yuan
- Nuclear Reactor Thermal Hydraulic Technology Key Laboratory, Nuclear Power Institute of China, Chengdu 610041, China
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Feng K, Wu Y, Hu J, Jin X, Gu H, Guo H. Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111622] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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18
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Wang Z, Guo K, Wang C, Zhang D, Tian W, Qiu S, Su G. Molecular dynamics study of liquid sodium film evaporation and condensation by Lennard-Jones potential. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.02.014] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Sun H, Liu X, Liao H, Wang C, Zhang J, Tian W, Qiu S, Su G. Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108760] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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20
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Ma Y, Liu J, Yu H, Tian C, Huang S, Deng J, Chai X, Liu Y, He X. Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.01.002] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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21
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Tang S, Liu X, Wang C, Zhang D, Su G, Tian W, Qiu S. Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108870] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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22
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Ma Y, Han W, Xie B, Yu H, Liu M, He X, Huang S, Liu Y, Chai X. Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111473] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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23
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Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111404] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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24
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Ma Y, Tian C, Yu H, Zhong R, Zhang Z, Huang S, Deng J, Chai X, Yang Y. Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103904] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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25
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Mueller C, Tsvetkov P. A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108393] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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26
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Mueller C, Tsvetkov P. A network approach to full core temperature analysis in advanced nuclear heat-pipe systems. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108354] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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27
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3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103790] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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28
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Kimura R, Nakai Y, Wada S. Reactor Core Power Distribution Reconstruction Method by Ex-Core Detectors Based on the Correlation Effect Between Fuel Regions. NUCL SCI ENG 2021. [DOI: 10.1080/00295639.2021.1908081] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- Rei Kimura
- Toshiba Energy Systems and Solutions Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, Japan
| | - Yuki Nakai
- Toshiba Energy Systems and Solutions Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, Japan
| | - Satoshi Wada
- Toshiba Energy Systems and Solutions Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, Japan
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30
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Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107923] [Citation(s) in RCA: 16] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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31
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Bustos J, Vergara JA, Correa FA. Development of a concept power plant using a Small Modular Reactor coupled with a Supercritical CO2 Brayton cycle for sustainable Antarctic stations. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2020.103606] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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32
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Wang D, Yan B, Chen J. The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107808] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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33
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Dwivedi D, Gupta A, Umasankari K. Analysis of unprotected loss of heat sink accident in compact high temperature reactor cooled under natural circulation of LBE coolant. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110881] [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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34
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Liu X, Zhang R, Liang Y, Tang S, Wang C, Tian W, Zhang Z, Qiu S, Su G. Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107412] [Citation(s) in RCA: 22] [Impact Index Per Article: 4.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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35
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