1 | A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber Yu, Hwanyeal; Yahya, Mohd Syukri; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.2, pp.318 - 329, 2016-04 |
2 | A study on a magnetic separation of radioactive corrosion products from NPP using permanent magnets Song, MC; Lee, Kun Jai, NUCLEAR ENGINEERING AND DESIGN, v.229, no.1, pp.101 - 111, 2004 |
3 | A Study on the Optimal Position for the Secondary Neutron Source in Pressurized Water Reactors![open access](/image/layout/oa_logo.png) Sun, Jungwon; Yahya, Mohd Syukri; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.6, pp.1291 - 1302, 2016-12 |
4 | (A) new approach for a high-performance soluble-boron-free PWR core = 고성능 무붕산 가압경수로 설계를 위한 새로운 접근link Yahya, Mohd Syukri; 야야, 모드 슈크리빈; et al, 한국과학기술원, 2016 |
5 | (A) study on optimal position for the secondary neutron source in PWRs = 가압경수로 2차 중성자 선원 위치 최적화 연구link Sun, Jung-Won; 선정원; et al, 한국과학기술원, 2014 |
6 | (A) study on the characteristics of cobalt adsorption on prepared $TiO_2$ and Fe-Ti-O adsorbents in high temperature water = 제조된 $TiO_2$ 및 Fe-Ti-O 흡착제의 고온수중에서 코발트흡착 특성연구link Kim, Kwang-Rag; 김광락; et al, 한국과학기술원, 1995 |
7 | (A) study on the conceptual design of a 2000 MWe pressurized water reactor = 2000 MWe 초대형 가압경수로 개념설계에 관한 연구link Chung, Yoon-Sun; 정윤선; et al, 한국과학기술원, 2002 |
8 | (A) study on the safety systems reliability analysis for a 2000 MWe pressureized water reactor = 2000 MWe 초대형 가압경수로 안전계통 신뢰도분석에 관한 연구link Huh, Jae-Young; 허재영; et al, 한국과학기술원, 2003 |
9 | Adsorption of cobalt(II) ion on prepared TiO2 adsorbents in high temperature water Kim, KR; Lee, KJ; Park, SeungBin, HIGH TEMPERATURE AND MATERIALS SCIENCE, v.35, no.2, pp.187 - 202, 1996-04 |
10 | An innovative core design for a soluble-boron-free small pressurized water reactor Yahya, Mohd Syukri; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.1, pp.73 - 81, 2018-01 |
11 | Development of CRUD thickness estimation model under pressurized water reactor condition = 가압경수로 조건에서의 크러드 두께 예측 모델 개발link Kim, Jegon; 김제곤; et al, 한국과학기술원, 2016 |
12 | Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing![open access](/image/layout/oa_logo.png) Lee, Tae Hyun; Ryu, Kyung Ha; Kim, Hong Deok; Hwang, Il Soon; Kim, Ji Hyun; Lee, Min Ho; Choi, Sungyeol, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.5, pp.1381 - 1389, 2019-08 |
13 | Experimental studies of boric acid precipitation in nuclear power plants during the post-LOCA long-term cooling period = 냉각재 상실사고 후 장기냉각에서 원자로 붕산석출에 관한 실험적 연구link Luo, Hu; 나호; et al, 한국과학기술원, 2008 |
14 | LEU plus loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme Khalefih, Husam; Oh, Taesuk; Jeong, Yunseok; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.7, pp.2578 - 2590, 2023-07 |
15 | Low-boron OPR1000 core based on the bigt burnable absorber = BigT 가연성흡수체를 활용한 저붕산 OPR1000 노심 설계link Yu, Hwan-Yeal; 유환열; et al, 한국과학기술원, 2014 |
16 | Physics conditions of passive autonomous frequency control operation in conventional large-size PWRs Abdelhameed, AAE; Lee, Jeong-Ik; Kim, Yonghee, PROGRESS IN NUCLEAR ENERGY, v.118, 2020-01 |
17 | Robotic suction nozzle design optimization for severe accident portable air-cleaning system Gu, Beom Woo; Choi, Su Yong; Yim, Man -Sung; Rim, Chun Taek, PROGRESS IN NUCLEAR ENERGY, v.89, pp.7 - 25, 2016-05 |
18 | Thermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel = 사용후 핵연료의 중간건식저장에 대한 열유체 실험 및 해석link Yoo, Seung-Hun; 류승훈; et al, 한국과학기술원, 2011 |
19 | Three-dimensional simulation of passive frequency regulations in the soluble-boron-free SMR ATOM Abdelhameed, Ahmed Amin E.; Kim, Yonghee, NUCLEAR ENGINEERING AND DESIGN, v.361, 2020-05 |
20 | Uncertainty and sensitivity analyses for fuel temperature evaluations of U-Mo/Al plate-type dispersion fuel Sweidan, Faris B.; Tahk, Young-Wook; Yim, Jeong-Sik; Ryu, Ho Jin, ANNALS OF NUCLEAR ENERGY, v.120, pp.581 - 592, 2018-10 |