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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