본문 바로가기

Data Plus(+)

All 807,818 Page 3,397/80,782

검색

Contents

No Journal_name Subject Date DOI Author
773858 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Numerical investigation of steady state characteristics and stability of supercritical water natural circulation loop of a heater and cooler arrangements 2021-11-25 10.1016/j.net.2021.05.026 Rai, Santosh Kumar, Kumar, Pardeep, Panwar, Vinay
773857 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY A cavitation performance prediction method for pumps: Part2-sensitivity and accuracy 2021-11-25 10.1016/j.net.2021.05.027 Long, Yun, Zhang, Yan, Chen, Jianping, Zhu, Rongsheng, Wang, Dezhong
773856 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Neutron spectroscopy using pure LaCl3 crystal and the dependence of pulse shape discrimination on Ce-doped concentrations 2021-11-25 10.1016/j.net.2021.05.020 Vuong, Phan Quoc, Kim, Hongjoo, Luan, Nguyen Thanh, Kim, Sunghwan
773855 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Tritium radioactivity estimation in cement mortar by heat-extraction and liquid scintillation counting 2021-11-25 10.1016/j.net.2021.06.004 Kang, Ki Joon, Bae, Jun Woo, Kim, Hee Reyoung
773854 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Dose evaluation of workers according to operating time and outflow rate in a spent resin treatment facility 2021-11-25 10.1016/j.net.2021.06.007 Byun, Jaehoon, Choi, Woo Nyun, Kim, Hee Reyoung
773853 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Sizing of a tube inlet orifice of a once-through steam generator to suppress the parallel channel instability 2021-11-25 10.1016/j.net.2021.06.003 Yoon, Juhyeon
773852 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Entropy, enthalpy, and gibbs free energy variations of 133Cs via CO2-activated carbon filter and ferric ferrocyanide hybrid composites 2021-11-25 10.1016/j.net.2021.06.006 Lee, Joon Hyuk, Suh, Dong Hack
773851 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Radioactivity analysis for EPS waste using organic solvents 2021-11-25 10.1016/j.net.2021.06.008 Bae, Jun Woo, Kim, Hee Reyoung
773850 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Experimental evaluation of fatigue strength for small diameter socket welded joints under vibration loading condition 2021-11-25 10.1016/j.net.2021.05.036 Oh, Chang-Young, Lee, Jun-Ho, Kim, Dong-Woo, Lee, Sang-Hoon
773849 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Fatigue life evaluation of socket welded pipe with incomplete penetration defect: I-test and FE analysis 2021-11-25 10.1016/j.net.2021.05.033 Lee, Dong-Min, Kim, Seung-Jae, Lee, Hyun-Jae, Kim, Yun-Jae