Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 221 to 240 of 10267
| A human-machine interface evaluation method: A difficulty evaluation method in information searching (DEMIS) Ha, Jun Su; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.94, no.10, pp.1557 - 1567, 2009-10 |
| A Hybrid (?,n) and (n,?) Transmutation Study for Long-living Fission Products Rehman, Haseeb Ur; Lee, Jiyoung; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1306 - 1309, American Nuclear Society, 2017-10 |
| A hybrid framework of worst-case execution time analysis for real-time embedded system software Lee J.-I.; Park S.-H.; Bang H.-J.; Kim T.-H.; Cha, Sungdeok, 2005 IEEE Aerospace Conference, v.2005, IEEE, 2005-03-05 |
| A hybrid-type scatter correction method for a single-scan cone-beam CT Min, Jonghwan; Pua, Rizza; Kim , Yejin; Cho, Seungryong, Fully Three-Dimensional Image Reconstruction in Radiology and Nuclear Medicine 2017(Fully 3D 2017), Fully3D, 2017-06-20 |
| A Knowledge-base Verification of NPP Expert Systems Using Extended Petri Nets Kwon, Il W; Seong, Poong-Hyun, The 1996 ANS International Topical Meeting on Nuclear I&C and Human-Machine Interface Technology, 1996-05 |
| A Knowledge-base Verification of NPP Expert Systems Using Extended Petri Nets Kwon, Il W.; Seong, Poong-Hyun, Korean Nuclear Society Autumn Meeting, 1995-10 |
| A Knowledge-based Expert System Using MFM Model for Operator Supporting Kun, Mo; Seong, Poong-Hyun, 한국원자력학회 2005 춘계학술발표대회, 한국원자력학회, 2005-05-26 |
| A Large Dry PWR Containment Response Analysis for Postulated Severe Accidents 전문헌, 한국원자력학회 '87 춘계학술발표회, pp.30 - 31, 1987 |
| A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters Kim, Yonghee; Hartanto, Donny; Kim, Woosong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.642 - 649, 2016-06 |
| A leakage correction with burnup-dependent GPS method in two-step core depletion analysis Jeong, Hae Sun; Oh, Taesuk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.183, 2023-04 |
| A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses Yu, Hwan Yeal; Kim, Woosong; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.129, pp.30 - 55, 2019-07 |
| A leakage correction with SPH factors for two-group cross-section in get-based pin-by-pin core analysis Yu, Hwan Yeal; Kim, Woosong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1229 - 1232, American Nuclear Society, 2018-11 |
| A Linear Multiple Balance Method for Discrete Ordinates Neutron Transport Equations Park, C.J.; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2000-10 |
| A linear multiple balance method with high order accuracy for discrete ordinates neutron transport equations Park, CJ; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.28, no.15, pp.1499 - 1517, 2001-10 |
| A low-power variable length decoder based on successive decoding of shoft codewords Lee, S.-W.; Park, In-Cheol, The 2001 International Symphosium on Circuits and Systems, pp.582 - 585, ISCAS, 2001-05-08 |
| A Lyapunov Function-Free Method for Stability Domains of Nonlinear Reactors Yang, C.Y; Cho, Nam-Zin, Proc. of the 1992 Topical Meeting on Advances in Reactor Physics, v.2, pp.433 - 444, 1992-03 |
| A Mass Conservative Numerical Solution of Vertical Water Flow and Mass Transport Equations in Unsaturated Porous Media Lee, Kun Jai, 1993 International Conference on Nuclear Waste Management and Environment Remediation, pp.525 - 531, 1993 |
| A Mass Conservative Numerical Solution of Vertical Water Flow and Mass Transport Equations in Unsaturated Porous Media seung cheol lim; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.20, no.2, pp.91 - 99, 1993 |
| A MEASURE OF THE DIFFICULTY OF SYSTEM DIAGNOSIS AND ITS RELATIONSHIP TO COMPLEXITY GOLAY, MW; Seong, Poong-Hyun; MANNO, VP, INTERNATIONAL JOURNAL OF GENERAL SYSTEMS, v.16, no.1, pp.1 - 23, 1989 |
| A Mechanistic CHF Model for Liquid Metals Based on Flow Excursion Mechanism Lee, YB; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, 1994 |
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