References
- D. Hartanto, I. Kim, C. Kim, Y. Kim, An LEU-loaded long-life innovative sodium-cooled fast reactor (iSFR) with novel and passive safety devices, Ann. Nucl. Energy 95 (2016) 86-101, https://doi.org/10.1016/j.anucene.2016.04.051.
- W.S. Yang, Fast reactor physics and computational methods, Nucl. Eng. Technol. 44 (2012) 177-198, https://doi.org/10.5516/NET.01.2012.504.
- D.G. Cacuci, Handbook of Nuclear Engineering, Springer Science & Business Media, New York, 2010.
- B. Merk, Fine distributed moderating material with improved thermal stability applied to enhance the feedback effects in SFR cores, Sci. Technol. Nucl. Install. 2013 (2013) 1-11, https://doi.org/10.1155/2013/217548.
- S.J. Kim, N.Z. Cho, Y.J. Kim, A pan-shape transuranic burner core with a low sodium void worth, Ann. Nucl. Energy 27 (2000) 435-448, https://doi.org/10.1016/S0306-4549(99)00101-2.
- C. Sciora, P., D. Blanchet, L. Buiron, B. Fontaine, M. Vanier, F. Varaine, Venard, Low void effect core design applied on 2400 MWth SFR reactor, in: International Congress on Advanced Nuclear Power Plants, Nice, France, 2011. May 2-5.
- M.F. Khalil, S.Z. Kassab, I.G. Adam, M. Samaha, Laminar flow in concentric annulus with a moving core, in: International Water Technology Conference, 2008. Alexandria, Egypt, March 27-30.
- I. Kim, T.F. Irvine, N.A. Park, Experimental study of the velocity field around a falling needle viscometer, Rev. Sci. Instrum. 65 (1994) 224-228, https:// doi.org/10.1063/1.1144789.
- E.G. Wehbeh, T.J. Ui, R.G. Hussey, End effects for the falling cylinder viscometer, Phys. Fluids A Fluid Dyn. 5 (2002) 25-33, https://doi.org/10.1063/1.858781.
- M.C.S. Chen, J.A. Lescarboura, G.W. Swift, The effect of eccentricity on the terminal velocity of the cylinder in a falling cylinder viscometer, AIChE J. 14 (1968) 123-127, https://doi.org/10.1002/aic.690140122.
- S. Lee, Y.H. Jeong, Floating absorber for safety at transient analysis code ( FASTAC ): verification and validation study, in: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Opereration and Safety, 2018. Qingdao, China, October 14-18.
- S.V. Patankar, Numerical Heat Transfer and Fluid Flow, first ed., CRC Press, Boca Raton, 1980.
- F.M. White, Fluid Mechanics, seventh ed., McGraw-Hill, New York, 2011.
- G. Biswas, M. Breuer, F. Durst, Backward-facing step flows for various expansion ratios at low and moderate Reynolds numbers, J. Fluids Eng. 126 (2004) 362-374, https://doi.org/10.1115/1.1760532.
- R.H. Anderson, D. Tannehill, J.C. Pletcher, Computational Fluid Mechanics and Heat Transfer, third ed., CRC Press, Boca Raton, 2016 https://doi.org/10.1201/b12884.
- A.S. Incropera, F.P., D.P. DeWitt, T.L. Bergman, Lavine, Foundations of Heat Transfer : International Student Version, sixth ed., John Wiley & Sons Ltd, 2012.
- H. Kazeminejad, Thermal-hydraulic modeling of reactivity insertion in a research reactor, Ann. Nucl. Energy 45 (2012) 59-67, https://doi.org/10.1016/ j.anucene.2012.02.017.
- J.R. Lamarsh, A.J. Baratta, Introduction to Nuclear Engineering, third ed., Prentice hall, Upper Saddle River, New Jersey, 2001.
- C. Housiadas, Lumped parameters analysis of coupled kinetics and thermal-hydraulics for small reactors, Ann. Nucl. Energy 29 (2002) 1315-1325, https://doi.org/10.1016/S0306-4549(01)00107-4.
- L. Leibowitz, R.A. Blomquist, Thermal conductivity and thermal expansion of stainless steels D9 and HT9, Int. J. Thermophys. 9 (1988) 873-883, https:// doi.org/10.1007/BF00503252.
- Y.S. Touloukian, R.W. Powell, C.Y. Ho, P.G. Klemens, Thermophysical Properties of Matter - the TPRC Data Series. Volume 1. Thermal Conductivity - Metallic Elements and Alloys, Plenum Press, New York, 1970.
- K.L. Lee, K.S. Ha, J.H. Jeong, C.W. Choi, T. Jeong, S.J. Ahn, S.W. Lee, W.P. Chang, S.H. Kang, J. Yoo, A preliminary safety analysis for the prototype gen IV sodium-cooled fast reactor, Nucl. Eng. Technol. 48 (2016) 1071-1082, https://doi.org/10.1016/j.net.2016.08.002.
- M.S. Dias, J.R.L.D, Mattos, Uranium-zirconium based alloys part I: reference points for thermophysical properties, in: International Nuclear Atlantic Conference, (Sao)
- Y. Chen, Irradiation effects of HT-9 martensitic steel, Nucl. Eng. Technol. 45 (2013) 311-322, https://doi.org/10.5516/NET.07.2013.706.
- R. Klueh, D. Harries, High-Chromium Ferritic and Martensitic Steels for Nuclear Applications, ASTM International, West Conshohocken, 2011.