Browse by Subject PWR

Showing results 12 to 21 of 21

12
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

13
Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing

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

14
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

15
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

16
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

17
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

18
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

19
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

20
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

21
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

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