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Deokjung Lee, Ph.D. - Publications

Affiliations: 
2003 Purdue University, West Lafayette, IN, United States 
Area:
Nuclear Engineering
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83 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2020 Yu J, Lee H, Kim H, Zhang P, Lee D. Coupled Neutronics–Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code System Nuclear Technology. 206: 728-742. DOI: 10.1080/00295450.2019.1677107  0.312
2020 Cherezov A, Jang J, Lee D. A PCA compression method for reactor core transient multiphysics simulation Progress in Nuclear Energy. 128: 103441. DOI: 10.1016/J.Pnucene.2020.103441  0.348
2020 Khoshahval F, Zhang P, Lee D. Analysis and comparison of direct inversion and Kalman filter methods for self-powered neutron detector compensation Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment. 969: 164097. DOI: 10.1016/J.Nima.2020.164097  0.33
2020 Ebiwonjumi B, Kong C, Zhang P, Cherezov A, Lee D. Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2020.07.012  0.338
2020 Jang J, Ebiwonjumi B, Kim W, Park J, Choe J, Lee D. Validation of spent nuclear fuel decay heat calculation by a two-step method Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2020.06.028  0.397
2020 Ta DL, Hong SG, Lee D. Validation of UNIST Monte Carlo Code MCS for Criticality Safety Calculations with Burnup Credit through MOX Criticality Benchmark Problems Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2020.06.016  0.346
2020 Setiawan F, Lemaire M, Lee D. Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2020.06.015  0.346
2020 Ebiwonjumi B, Lee H, Kim W, Lee D. Validation of nuclide depletion capabilities in Monte Carlo code MCS Nuclear Engineering and Technology. 52: 1907-1916. DOI: 10.1016/J.Net.2020.02.017  0.381
2020 Dos V, Lee H, Jo Y, Lemaire M, Kim W, Choi S, Zhang P, Lee D. Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code Nuclear Engineering and Technology. 52: 1881-1895. DOI: 10.1016/J.Net.2020.02.003  0.383
2020 Lemaire M, Lee H, Zhang P, Lee D. Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCS Nuclear Engineering and Technology. 52: 1355-1366. DOI: 10.1016/J.Net.2019.12.014  0.33
2020 Nguyen TDC, Lee H, Choi S, Lee D. Validation of UNIST Monte Carlo code MCS using VERA progression problems Nuclear Engineering and Technology. 52: 878-888. DOI: 10.1016/J.Net.2019.10.023  0.384
2020 Yu J, Lee H, Kim H, Zhang P, Lee D. Simulations of BEAVRS benchmark cycle 2 depletion with MCS/CTF coupling system Nuclear Engineering and Technology. 52: 661-673. DOI: 10.1016/J.Net.2019.09.007  0.348
2020 Choi S, Lee D. Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation Computer Physics Communications. 107332. DOI: 10.1016/J.Cpc.2020.107332  0.377
2020 Yu J, Lee H, Kim H, Zhang P, Lee D. Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS Computer Physics Communications. 251: 106748. DOI: 10.1016/J.Cpc.2019.03.001  0.367
2020 Tran TQ, Choe J, Du X, Lee H, Lee D. Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation Annals of Nuclear Energy. 148: 107710. DOI: 10.1016/J.Anucene.2020.107710  0.332
2020 Lee H, Kim W, Zhang P, Lemaire M, Khassenov A, Yu J, Jo Y, Park J, Lee D. MCS – A Monte Carlo particle transport code for large-scale power reactor analysis Annals of Nuclear Energy. 139: 107276. DOI: 10.1016/J.Anucene.2019.107276  0.378
2020 Nguyen TDC, Lee H, Choi S, Lee D. MCS/TH1D analysis of VERA whole-core multi-cycle depletion problems Annals of Nuclear Energy. 139: 107271. DOI: 10.1016/J.Anucene.2019.107271  0.381
2020 Yu J, Lee H, Lemaire M, Kim H, Zhang P, Lee D. Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled system Annals of Nuclear Energy. 138: 107192. DOI: 10.1016/J.Anucene.2019.107192  0.389
2020 Du X, Choe J, Tran TQ, Lee D. Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation Annals of Nuclear Energy. 136: 107046. DOI: 10.1016/J.Anucene.2019.107046  0.354
2020 Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D. Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor Annals of Nuclear Energy. 136: 107034. DOI: 10.1016/J.Anucene.2019.107034  0.381
2020 Mai NNT, Zhang P, Lemaire M, Ebiwonjumi B, Kim W, Lee H, Lee D. Extension of Monte Carlo code MCS to spent fuel cask shielding analysis International Journal of Energy Research. 44: 8089-8102. DOI: 10.1002/Er.5023  0.334
2019 Du X, Choe J, Choi S, Lee W, Cherezov A, Lim J, Lee M, Lee D. Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis Nuclear Engineering and Technology. 51: 1871-1885. DOI: 10.1016/J.Net.2019.06.010  0.39
2019 Choe J, Choi S, Zhang P, Park J, Kim W, Shin HC, Lee HS, Jung J, Lee D. Verification and validation of STREAM/RAST-K for PWR analysis Nuclear Engineering and Technology. 51: 356-368. DOI: 10.1016/J.Net.2018.10.004  0.344
2019 Yu J, Lee H, Lemaire M, Kim H, Zhang P, Lee D. MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON Computer Physics Communications. 238: 1-18. DOI: 10.1016/J.Cpc.2019.01.001  0.358
2019 Park J, Zhang P, Lee H, Choi S, Yu J, Lee D. Performance evaluation of CMFD on inter-cycle correlation reduction of Monte Carlo simulation Computer Physics Communications. 235: 111-119. DOI: 10.1016/J.Cpc.2018.09.014  0.39
2019 Jeong E, Park J, Lee HC, Zhang P, Yu J, Lemaire M, Choi S, Lee D. Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark Annals of Nuclear Energy. 133: 154-168. DOI: 10.1016/J.Anucene.2019.05.002  0.366
2019 Park J, Kim W, Hursin M, Perret G, Vasiliev A, Rochman D, Pautz A, Ferroukhi H, Lee D. Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5 Annals of Nuclear Energy. 131: 9-22. DOI: 10.1016/J.Anucene.2019.03.023  0.316
2019 Kong C, Lee D. Sensitivity analysis of source intensity and time bin size for the Rossi-alpha method in a numerical reactor model Annals of Nuclear Energy. 130: 157-163. DOI: 10.1016/J.Anucene.2019.02.040  0.318
2019 Kim MJ, Kim W, Lee D, Lemaire M, Lee H, Sohn D, Kwon H. Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials Annals of Nuclear Energy. 130: 107-117. DOI: 10.1016/J.Anucene.2019.02.027  0.306
2019 Zhang P, Lee H, Lemaire M, Kong C, Choe J, Yu J, Khoshahval F, Lee D. Practical Monte Carlo simulation using modified power method with preconditioning Annals of Nuclear Energy. 127: 372-384. DOI: 10.1016/J.Anucene.2018.12.023  0.354
2019 Park J, Khassenov A, Kim W, Choi S, Lee D. Comparative analysis of VERA depletion benchmark through consistent code-to-code comparison Annals of Nuclear Energy. 124: 385-398. DOI: 10.1016/J.Anucene.2018.10.024  0.353
2019 Ebiwonjumi B, Choi S, Lemaire M, Lee D, Shin HC, Lee HS. Verification and validation of radiation source term capabilities in STREAM Annals of Nuclear Energy. 124: 80-87. DOI: 10.1016/J.Anucene.2018.09.034  0.318
2019 Nguyen KHN, Choi S, Lemaire M, Lee D. Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysis Annals of Nuclear Energy. 123: 18-45. DOI: 10.1016/J.Anucene.2018.08.030  0.404
2018 Tran TQ, Jeong S, Nguyen KHN, Lee H, Choi S, Zhang P, Lee MJ, Lim JY, Lee D. Validation of the MCNP6 code for SFR shielding design analysis. Journal of Radiological Protection : Official Journal of the Society For Radiological Protection. PMID 30238929 DOI: 10.1088/1361-6498/Aae323  0.337
2018 Lemaire M, Lee H, Ebiwonjumi B, Kong C, Kim W, Jo Y, Park J, Lee D. Verification of photon transport capability of UNIST Monte Carlo code MCS Computer Physics Communications. 231: 1-18. DOI: 10.1016/J.Cpc.2018.05.008  0.312
2018 Zhang P, Lee H, Lee D. On the Transfer Matrix of the Modified Power Method Computer Physics Communications. 222: 102-112. DOI: 10.1016/J.Cpc.2017.09.022  0.309
2018 Khoshahval F, Yum S, Shin HC, Choe J, Zhang P, Lee D. Smart sensing of the axial power and offset in NPPs using GMDH method Annals of Nuclear Energy. 121: 77-88. DOI: 10.1016/J.Anucene.2018.07.007  0.31
2018 Ebiwonjumi B, Choi S, Lemaire M, Lee D, Shin HC. Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory Annals of Nuclear Energy. 120: 431-449. DOI: 10.1016/J.Anucene.2018.06.002  0.36
2018 Jang J, Kim W, Jeong S, Jeong E, Park J, Lemaire M, Lee H, Jo Y, Zhang P, Lee D. Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask Annals of Nuclear Energy. 114: 495-509. DOI: 10.1016/J.Anucene.2017.12.054  0.375
2018 Park J, Han TY, Lee D, Lee HC. VHTR core analysis with McCARD and DeCART codes for high temperature engineering test reactor benchmark Annals of Nuclear Energy. 114: 42-51. DOI: 10.1016/J.Anucene.2017.12.005  0.356
2018 Khoshahval F, Park M, Shin HC, Zhang P, Lee D. Vanadium, rhodium, silver and cobalt self-powered neutron detector calculations by RAST-K v2.0 Annals of Nuclear Energy. 111: 644-659. DOI: 10.1016/J.Anucene.2017.09.048  0.353
2018 Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A. Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code Annals of Nuclear Energy. 111: 141-151. DOI: 10.1016/J.Anucene.2017.08.061  0.386
2017 Zhang P, Lee H, Lee D. Monte Carlo Inter-Cycle Correlation Reduction with the Application of the Modified Power Method Destech Transactions On Engineering and Technology Research. DOI: 10.12783/Dtetr/Amsm2017/14839  0.321
2017 Lemaire M, Lee H, Tak N, Lee HC, Lee D. Multi-physics steady-state analysis of OECD/NEA modular high temperature gas-cooled reactor MHTGR-350 Journal of Nuclear Science and Technology. 54: 668-680. DOI: 10.1080/00223131.2017.1299649  0.325
2017 Choi S, Smith KS, Kim H, Tak T, Lee D. On the diffusion coefficient calculation in two-step light water reactor core analysis Journal of Nuclear Science and Technology. 54: 705-715. DOI: 10.1080/00223131.2017.1299648  0.36
2017 Zhang P, Lee H, Lee D. Calculation of Degenerated Eigenmodes with Modified Power Method Nuclear Engineering and Technology. 49: 17-28. DOI: 10.1016/J.Net.2016.08.009  0.354
2017 Park J, Lee H, Tak T, Shin HC, Lee D. Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis Nuclear Engineering and Technology. 49: 6-16. DOI: 10.1016/J.Net.2016.07.003  0.32
2017 Zheng Y, Choi S, Lee D. A new approach to three-dimensional neutron transport solution based on the method of characteristics and linear axial approximation Journal of Computational Physics. 350: 25-44. DOI: 10.1016/J.Jcp.2017.08.026  0.33
2017 Choi S, Lee C, Lee D. Resonance treatment using pin-based pointwise energy slowing-down method Journal of Computational Physics. 330: 134-155. DOI: 10.1016/J.Jcp.2016.11.007  0.344
2017 Zheng Y, Lee D, Zhang P, Lee E, Shin H. Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulation Annals of Nuclear Energy. 101: 139-150. DOI: 10.1016/J.Anucene.2016.11.002  0.381
2017 Kim H, Choi S, Park M, Lee D, Lee HC. Extension of double heterogeneity treatment method for coated TRISO fuel particles Annals of Nuclear Energy. 99: 124-135. DOI: 10.1016/J.Anucene.2016.07.026  0.311
2017 Kong C, Lee D, Shin HC. Lifetime extension of in-core self-powered neutron detector using new emitter materials International Journal of Energy Research. 41: 2405-2412. DOI: 10.1002/Er.3817  0.311
2017 Park J, Tak T, Kim TK, Choe J, Jeong Y, Zhang P, Lee D. Design study of long-life small modular sodium-cooled fast reactor International Journal of Energy Research. 41: 139-148. DOI: 10.1002/Er.3609  0.314
2016 Choi S, Khassenov A, Lee D. Resonance self-shielding method using resonance interference factor library for practical lattice physics computations of LWRs Journal of Nuclear Science and Technology. 53: 1142-1154. DOI: 10.1080/00223131.2015.1095686  0.353
2016 Kim W, Lee HC, Pyeon CH, Shin HC, Lee D. Monte Carlo Analysis of the Accelerator-Driven System at Kyoto University Research Reactor Institute Nuclear Engineering and Technology. 48: 304-317. DOI: 10.1016/J.Net.2015.12.001  0.347
2016 Zhang P, Lee H, Lee D. Extension of modified power method to two-dimensional problems Journal of Computational Physics. 320: 17-32. DOI: 10.1016/J.Jcp.2016.05.024  0.326
2016 Zhang P, Lee H, Lee D. A general solution strategy of modified power method for higher mode solutions Journal of Computational Physics. 305. DOI: 10.1016/J.Jcp.2015.10.042  0.35
2016 Choe J, Shin HC, Lee D. New burnable absorber for long-cycle low boron operation of PWRs Annals of Nuclear Energy. 88: 272-279. DOI: 10.1016/J.Anucene.2015.11.011  0.313
2016 Tak T, Zheng Y, Lee D, Kim TK. Power flattening study of ultra-long cycle fast reactor using thorium fuel International Journal of Energy Research. 40: 1662-1672. DOI: 10.1002/Er.3552  0.317
2016 Choe J, Lee D, Jung JE, Shin HC. Performance evaluation of Zircaloy reflector for pressurized water reactors International Journal of Energy Research. 40: 160-167. DOI: 10.1002/Er.3443  0.368
2015 Choi S, Kong C, Lee D, Williams ML. A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel - II. Verifications Nuclear Science and Engineering. 180: 41-57. DOI: 10.13182/Nse14-72  0.383
2015 Williams ML, Choi S, Lee D. A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—I: Theory Nuclear Science and Engineering. 180: 30-40. DOI: 10.13182/Nse14-68  0.353
2015 Lee H, Choi S, Lee D. A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport Analysis Nuclear Science and Engineering. 180: 69-85. DOI: 10.13182/Nse13-102  0.369
2015 Kim W, Park J, Kozlowski T, Lee HC, Lee D. Comparative neutronics analysis of DIMPLE S06 criticality benchmark with contemporary reactor core analysis computer code systems Science and Technology of Nuclear Installations. 2015. DOI: 10.1155/2015/180979  0.601
2015 Jeong Y, Park J, Lee HC, Lee D. Equilibrium core design methods for molten salt breeder reactor based on two-cell model Journal of Nuclear Science and Technology. DOI: 10.1080/00223131.2015.1062812  0.347
2015 Choi S, Lee H, Hong SG, Lee D. Resonance self-shielding methodology of new neutron transport code STREAM Journal of Nuclear Science and Technology. 52: 1133-1150. DOI: 10.1080/00223131.2014.993738  0.319
2015 Lee H, Choi S, Cha K, Lee K, Lee D. New calculational model for self-powered neutron detector based on Monte Carlo simulation Journal of Nuclear Science and Technology. 52: 660-669. DOI: 10.1080/00223131.2014.975766  0.377
2015 Hong SG, Lee D. Sub-cell balanced nodal expansion methods using S4 eigenfunctions for multi-group SN transport problems in slab geometry Journal of Nuclear Science and Technology. 52: 315-331. DOI: 10.1080/00223131.2014.949892  0.342
2015 Jeong Y, Park J, Lee HC, Lee D. Convergence analysis of two-node CMFD method for two-group neutron diffusion eigenvalue problem Journal of Computational Physics. 302: 239-250. DOI: 10.1016/J.Jcp.2015.09.004  0.302
2015 Choi S, Smith K, Lee HC, Lee D. Impact of inflow transport approximation on light water reactor analysis Journal of Computational Physics. 299: 352-373. DOI: 10.1016/J.Jcp.2015.07.005  0.342
2015 Lee D, Kozlowski T, Downar TJ. Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident Annals of Nuclear Energy. 77: 94-100. DOI: 10.1016/J.Anucene.2014.10.019  0.7
2015 Park J, Jeong Y, Lee HC, Lee D. Whole core analysis of molten salt breeder reactor with online fuel reprocessing International Journal of Energy Research. 39: 1673-1680. DOI: 10.1002/Er.3371  0.342
2014 Tak T, Lee D, Kim TK, Hong SG. Optimization study of Ultra-long Cycle Fast Reactor core concept Annals of Nuclear Energy. 73: 145-161. DOI: 10.1016/J.Anucene.2014.06.030  0.308
2014 Lee MJ, Joo HG, Lee D, Smith K. Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation Annals of Nuclear Energy. 65: 101-113. DOI: 10.1016/J.Anucene.2013.10.025  0.382
2013 Lee D, Rhodes J, Smith K. Quadratic Depletion Method for Gadolinium Isotopes in CASMO-5 Nuclear Science and Engineering. 174: 79-86. DOI: 10.13182/Nse12-20  0.318
2012 Lee D. Convergence analysis of coarse mesh finite difference method applied to two-group three-dimensional neutron diffusion problem Journal of Nuclear Science and Technology. 49: 926-936. DOI: 10.1080/00223131.2012.712478  0.315
2011 Kozlowski T, Xu Y, Downar TJ, Lee D. Cell homogenization method for pin-by-pin neutron transport calculations Nuclear Science and Engineering. 169: 1-18. DOI: 10.13182/Nse08-85  0.723
2009 Lee D, Smith K, Rhodes J. The impact of 238U resonance elastic scattering approximations on thermal reactor Doppler reactivity Annals of Nuclear Energy. 36: 274-280. DOI: 10.1016/J.Anucene.2008.11.026  0.316
2007 Lee HC, Noh JM, Joo HK, Lee D, Downar TJ. Fourier convergence analysis of two-dimensional/one-dimensional coupling methods for the three-dimensional neutron diffusion eigenvalue problems Nuclear Science and Engineering. 156: 74-85. DOI: 10.13182/Nse06-32  0.604
2005 Lee HC, Lee D, Downar TJ. Iterative two- and one-dimensional methods for three-dimensional neutron diffusion calculations Nuclear Science and Engineering. 151: 46-54. DOI: 10.13182/Nse04-68  0.603
2004 Lee D, Downar TJ, Ulses A, Akdeniz B, Ivanov KN. Analysis of the OECD/NRC BWR turbine trip transient benchmark with the coupled thermal-hydraulics and neutronics code TRAC-M/PARCS Nuclear Science and Engineering. 148: 291-305. DOI: 10.13182/Nse04-A2459  0.592
2004 Lee D, Downar TJ, Kim Y. A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations Nuclear Science and Engineering. 146: 319-339. DOI: 10.13182/Nse04-A2412  0.613
2004 Lee D, Downar TJ, Kim Y. Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem Nuclear Science and Engineering. 147: 127-147. DOI: 10.13182/Nse03-64  0.572
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