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atw - International Journal for Nuclear Power | 01.2020

Ever since its first issue in 1956, the atw – International Journal for Nuclear Power has been a publisher of specialist articles, background reports, interviews and news about developments and trends from all important sectors of nuclear energy, nuclear technology and the energy industry. Internationally current and competent, the professional journal atw is a valuable source of information. www.nucmag.com

Ever since its first issue in 1956, the atw – International Journal for Nuclear Power has been a publisher of specialist articles, background reports, interviews and news about developments and trends from all important sectors of nuclear energy, nuclear technology and the energy industry. Internationally current and competent, the professional journal atw is a valuable source of information.

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<strong>atw</strong> Vol. 65 (2020) | Issue 1 ı January<br />

RESEARCH AND INNOVATION 44<br />

References:<br />

[1] J.A. Kulesza, F. Franceschini, T.M. Evans, et al, Overview of<br />

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[6] Y. Liu, Y.P. Liu, S.M. Tao et al. Three-dimensional analysis of<br />

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[7] J. Jang, H. Arastoopour. CFD simulation of a pharmaceutical<br />

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[8] D.L. Zhang a, b, S.Z. Qiu a, b,*, G.H. Sua, b, C.L. Liu b. Development<br />

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[9] X.W. Gui, Q. Cai, Y.Q. Chen. Study on coupling of local threedimension<br />

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and Enginee ring, 2010 (3): 216-222.<br />

[10] Klas Jareteg, Paolo Vinai, Christophe Demazière. Fine-mesh<br />

deterministic modeling of PWR fuel assemblies:Proof-ofprinciple<br />

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[J]. Annals of <strong>Nuclear</strong> Energy, 2014, 68:247-256.<br />

[11] Chen H, Zhang X, Zhao Y, et al. Preliminary design of a<br />

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[12] Li S, Cao L, Khan MS, Chen H. Development of a sub-channel<br />

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[13] Ahmad Pirouzmand-Abolhasan Nabavi. Simulation of<br />

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[15] ANSYS, 2013. ANSYS FLUENT Theory Guide, Release 15.0.<br />

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[17] G.W. Bi. Interpolation method development <strong>for</strong> temperature<br />

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[20] Chen Z. Thermal-hydraulics design and safety analysis of a<br />

100MWth small natural circulation lead cooled fast reactor<br />

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[21] Popov, S.G., Carbajo, J.J., Ivanov, V.K., Yoder, G.L., 2000.<br />

Thermophysical properties of MOX and UO2 fuels including<br />

the effects of irradiation. ORNL Report TM-2000/351.<br />

Authors<br />

Xuebei Zhang<br />

Chi Wang<br />

Hongli Chen<br />

School of Physics,<br />

University of Science & Technology<br />

of China<br />

Hefei 230027<br />

China<br />

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ISSN 1431-5254<br />

Research and Innovation<br />

Research on Neutron Diffusion and Thermal Hydraulics Coupling Calculation based on FLUENT and its Application Analysis on Fast Reactors ı Xuebei Zhang, Chi Wang and Hongli Chen

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