Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 1801 to 1820 of 10364
| Assessment of fuel cycle proliferation resistance dynamics using coupled isotopic characterization Skutnik, Steven E.; Yim, Man-Sung, NUCLEAR ENGINEERING AND DESIGN, v.241, no.8, pp.3270 - 3282, 2011-08 |
| Assessment of geometric uncertainties in gated stereotactic ablative body radiotherapy(SABR) Chung, H; Cho, B; Cho, Seungryong, The 7th Korea-Japan Joint Meeting on Medical Physics, KJMP, 2014-09-26 |
| Assessment of High Chromium Oxide Dispersion Strengthened Steels for Nuclear Applications Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., EUROMAT 2005, 2005-09-20 |
| Assessment of HTGR helium compressor analysis tool based on Newton-Raphson numerical application to throughflow analysis Kim, J.H.; Kim, H.M.; No, Hee Cheon, Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14, 2006-07-17 |
| Assessment of Nominal Ionosphere Spatial Decorrelation for LAAS Lee, Ji Hyun; Pullen, Sam; Datta-Barua, Seebany; Enge, Per, 2006 IEEE/ION Position, Location, And Navigation Symposium, 2010-11 |
| Assessment of passive containment cooling concepts for advanced pressurized water reactors Lee, SW; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.24, no.6, pp.467 - 475, 1997-04 |
| Assessment of pool boiling CHF enhancement using magnetite and alumina water nanofluids at higher pressure Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10 |
| Assessment of Potential Radiation Exposures by Uncontrolled Recycle or Reuse of Radioactive Scrap Metals sang-yoon lee; Lee, Kun Jai, WASTE MANAGEMENT, v.19, no.7-8, pp.483 - 493, 1999 |
| Assessment of Proliferation Resistance of Nuclear Reactor Systems Using Fuzzy Logic Based Barrier Method Jun Li; Yim Man-Sung; David N. McNelis, INMM (Institute of Nuclear Materials Management) 46th Annual Meeting, INMM (Institute of Nuclear Materials Management) 46th Annual Meeting, 2005-07 |
| Assessment of proliferation resistance of nuclear reactors using fuzzy logic based barrier method Li Jun; Yim Man-Sung; McNelis, David N., 2005 Annual Meeting - American Nuclear Society, v.92, no.2005, pp.276 - 277, Transactions of the American Nuclear Society, 2005-06 |
| Assessment of Proliferation Resistance of Nuclear Reactors Using Fuzzy Logic Based Barrier Method Jun Li; Yim Man-Sung; David N. McNelis, Transactions of the American Nuclear Society, v.92, no.2005, pp.276 - 277, American Nuclear Society, 2005-06 |
| Assessment of PSD impact by pile-up effect and three-dimensional PSD method for high gamma-ray field Song, Gyohyeok; Lee, Sangho; Kim, Wonku; Hwang, Jisung; Kim, Junhyeok; Ko, Kilyoung; Park, Jaehyun; et al, 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conferenc, IEEE NPSS, 2022-11-08 |
| Assessment of RELAP5/MOD3 with Condensation Experiment for Pure Steam Condensation in a Vertical Tube No, Hee Cheon; Kim, Sang Jae, 한국원자력학회 춘계발표회, 한국원자력학회, 1998 |
| Assessment of RELAP5/MOD3.1 for direct-contact condensation in the core makeup tank of the CAPP passive reactor ILLee, S; No, Hee Cheon, ANNALS OF NUCLEAR ENERGY, v.24, no.7, pp.553 - 562, 1997-05 |
| Assessment of RELAP5/MOD3.2 with Condensation Experiment in the Presence of Noncondensables in a Vertical Tube No, Hee Cheon; Park, Hyun Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 1998 |
| Assessment of RELAP5/MOD3.2.2 gamma against flooding database in horizontal-to-inclined pipes Kim, HT; No, Hee Cheon, ANNALS OF NUCLEAR ENERGY, v.29, no.7, pp.835 - 850, 2002-05 |
| Assessment of RELAP5/MOD3.2.2γ Against Flooding Database in Horizontal-to-Inclined Pipes No, Hee Cheon; Kim, Hyoung Tae, 한국원자력학회 춘계발표회, 한국원자력학회, 2001 |
| Assessment of SPACE by Reflood Experiments with the Consideration of Hysteresis during Boiling Heat Transfer 정운호; 정용훈, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-25 |
| Assessment of straight, zigzag, S-shape, and airfoil PCHEs for intermediate heat exchangers of HTGRs and SFRs Yoon, Seung Hyun; No, Hee Cheon; Kang, Gil Beom, NUCLEAR ENGINEERING AND DESIGN, v.270, pp.334 - 343, 2014-04 |
| Assessment of surface fatigue crack behavior on NPP piping under seismic loading = 지진하중 특성을 고려한 원전 배관의 표면피로균열 거동 평가link Wang, Wung Jae; Yim, Man-Sung; et al, 한국과학기술원, 2023 |
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