Lee, Yoonhee
(Korea Institute of Nuclear Safety)
Cho, Bumhee (Standard Energy) Cho, Nam Zin (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) |
1 | M. Umeda, T. Sugiyama, F. Nagase, T. Fuketa, S. Ueta, K. Sawa, Behavior of coated fuel particle of high-temperature gas-cooled reactor under reactivity-initiated accident conditions, J. Nucl. Sci. Technol. 47 (2010) 991-997. DOI |
2 | A.C. Kadak, R.G. Ballinger, M.J. Driscoll, S. Yip, D.G. Wilson, H.C. No, J. Wang, H. MacLean, T. Galen, C. Wang, J. Lebenhaft, T. Zhai, D.A. Petti, W.K. Terry, H.D. Gougar, A.M. Ougouag, C.H. Oh, R.L. Moore, G.K. Miller, J.T. Maki, G.R. Smolik, D.J. Varacalle, Modular Pebble Bed Reactor Project: University Research Consortium Annual Report, INEEL/EXT-2000-01034, Idaho National Engineering & Environmental Laboratory, 2000. |
3 | R. Hidayatullah, D. Hartanto, Y. Kim, A novel research reactor concept based on coated particle,, Ann. Nucl. Energy 77 (2015) 477-486. DOI |
4 | D. Hartanto, Y. Kim, F. Venneri, Neutronics evaluation of a super-deep-burn with TRU fully ceramic microencapsulated (FCM) fuel in CANDU, Prog. Nucl. Energy 83 (2015) 261-269. DOI |
5 | Y. Lee, B. Cho, N.Z. Cho, Steady- and transient-state analyses of fully ceramic microencapsulated fuel with randomly dispersed TRISO particles via two-temperature homogenized modeldI: theory and method, Nucl. Eng. Technol. 48 (2016) 650-659. DOI |
6 | H. Yu, N.Z. Cho, Comparison of Monte Carlo simulation models for randomly distributed particle fuels in VHTR Fuel Element, Trans. Am. Nucl. Soc. 95 (2006) 719-721. |
7 | L.L. Snead, T. Nozawa, Y. Katoh, T.-S. Byun, S. Kondo, D.A. Petti, Handbook of SiC properties for fuel performance modeling, J. Nucl. Mater. 371 (2007) 329-377. DOI |
8 | B. Cho, N.Z. Cho, Y. Kim, Theory Manual for the Rectangular Three-Dimensional Diffusion Nodal Code COREDAX-2 Version 1.5, KINS/HR-1356 Rev. 1, NURAPT-2015-02, Korea Advanced Institute of Science and Technology/Korea Institute of Nuclear Safety, 2015. |
9 | S.B. Ross, M.S. El-Genk, Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K, J. Nucl. Mater. 151 (1988) 313-317. DOI |
10 | IAEA, Thermophysical Properties Database of Materials for Light Water Reactor and Heavy Water Reactors, IAEA-TECDOC-1496, Vienna (Austria), 2006. |
11 | K.A. Terrani, J.O. Kiggans, C.M. Silva, C. Shih, Y. Katoh, L.L. Snead, Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form, J. Nucl. Mater. 457 (2015) 9-17. DOI |
12 | J. Leppanen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: status, development and application in 2013, Ann. Nucl. Eergy 82 (2015) 142-150. DOI |
13 | R.E. MacFarlane, D.W. Muir, R.M. Boicourt, A.C. Kahler, The NJOY Nuclear Data Processing System, Version 2012, LA-UR-12-27079, Los Alamos National Laboratory, 2012. |
14 | J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons Inc., New York, 1975. |
15 | J.D. Stempien, Behavior of Triplex Silicon Carbide Fuel Cladding Designs Tested under Simulated PWR Conditions, MS Thesis, MIT, Cambridge (MA), 2011. |