Acknowledgement
This work was supported by the Mass Production Performance Assessment Program (1415171778), the Materials & Components Technology Development Program (1415171720, 1415171728), the Technology Innovation Program (20011164), and the Energy Technology Development Program (20215810100050) funded by the Korean Government Ministry of Trade, Industry and Energy.
References
- Generation IV International Forum, Technology Roadmap Update for Generation IV Nuclear Energy Systems, OECD Nuclear Energy Agency, Paris, France, 2014.
- K. Tucek, J. Carlsson, H. Wider, Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues, Nucl. Eng. Des. 236 (2006) 1589-1598, https://doi.org/10.1016/j.nucengdes.2006.04.019.
- S. Choi, J.-H. Cho, M.-H. Bae, J. Lim, D. Puspitarini, J.H. Jeun, H.-G. Joo, I.S. Hwang, PASCAR: long burning small modular reactor based on natural circulation, Nucl. Eng. Des. 241 (2011) 1486-1499, https://doi.org/10.1016/j.nucengdes.2011.03.005.
- Y.-H. Shin, S. Choi, J. Cho, J.H. Kim, I.S. Hwang, Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation, Prog. Nucl. Energy 83 (2015) 433-442, https://doi.org/10.1016/j.pnucene.2015.01.002.
- J.J. Sienicki, B.W. Spencer, Power optimization in the STAR-LM modular natural convection reactor system, American Society of Mechanical Engineers Digital Collection, 2009, pp. 685-690, https://doi.org/10.1115/ICONE10-22294.
- D.C. Wade, E. Feldman, J. Sienicki, T. Sofu, A. Barak, E. Greenspan, D. Saphier, N.W. Brown, Q. Hossain, M.D. Carelli, L. Conway, M. Dzodzo, ENHS: the encapsulated nuclear heat source - a nuclear Energy concept for emerging worldwide Energy markets, American Society of Mechanical Engineers Digital Collection, 2009, pp. 583-590, https://doi.org/10.1115/ICONE10-22202.
- J.H. Cho, A. Batta, V. Casamassima, X. Cheng, Y.J. Choi, I.S. Hwang, J. Lim, P. Meloni, F.S. Nitti, V. Dedul, V. Kuznetsov, O. Komlev, W. Jaeger, A. Sedov, J.H. Kim, D. Puspitarini, Benchmarking of thermal hydraulic loop models for Lead-Alloy Cooled Advanced Nuclear Energy System (LACANES), phase-I: isothermal steady state forced convection, J. Nucl. Mater. 415 (2011) 404-414, https://doi.org/10.1016/j.jnucmat.2011.04.043.
- A. Batta, J. Cho, A. Class, I. Hwang, CFD analysis of heavy liquid metal flow in the core of the HELIOS loop, Nuclear Engineering and Technology (2010) 42, https://doi.org/10.5516/NET.2010.42.6.656.
- K. Rehme, Pressure drop correlations for fuel element spacers, Nucl. Technol. 17 (1973) 15-23, https://doi.org/10.13182/NT73-A31250.
- M. Cigarini, M. Dalle Donne, Thermohydraulic optimization of homogeneous and heterogeneous advanced pressurized water reactors, Nucl. Technol. 80 (1988) 107-132, https://doi.org/10.13182/NT88-A35553.
- S.C. Yao, L.E. Hochreiter, W.J. Leech, Heat-transfer augmentation in rod bundles near grid spacers, J. Heat Tran. 104 (1982) 76-81, https://doi.org/10.1115/1.3245071.
- M. Schikorr, E. Bubelis, L. Mansani, K. Litfin, Proposal for pressure drop prediction for a fuel bundle with grid spacers using Rehme pressure drop correlations, Nucl. Eng. Des. 240 (2010) 1830-1842, https://doi.org/10.1016/j.nucengdes.2010.03.039.
- F. Roelofs (Ed.), Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, Elsevier, 2019, https://doi.org/10.1016/C2016-0-01216-0.
- OECD Nuclear Energy Agency, Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies, 2015 edition, OECD Nuclear Energy Agency, Paris, France, 2015.