Browse by Subject PWR

Showing results 1 to 18 of 18

1

A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber

Yu, Hwanyeal; Yahya, Mohd Syukri; Kim, Yongheeresearcher, 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 Jairesearcher, 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

Sun, Jungwon; Yahya, Mohd Syukri; Kim, Yongheeresearcher, 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, SeungBinresearcher, 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, Yongheeresearcher, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.1, pp.73 - 81, 2018-01

11

Break-Even Point Analysis of Sodium-Cooled Fast Reactor Capital Investment Cost Comparing the Direct Disposal Option and Pyro-Sodium-Cooled Fast Reactor Nuclear Fuel Cycle Option in Korea

Kim, Sungki; Jang, Hong; Gao, Ruxing; Kim, Chulmin; Chung, Yanghonresearcher; Bang, Sungsig, SUSTAINABILITY, v.9, no.9, pp.1518, 2017-09

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, Sungyeolresearcher, 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

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

Robotic suction nozzle design optimization for severe accident portable air-cleaning system

Gu, Beom Woo; Choi, Su Yong; Yim, Man -Sungresearcher; Rim, Chun Taekresearcher, PROGRESS IN NUCLEAR ENERGY, v.89, pp.7 - 25, 2016-05

17

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

18

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 Jinresearcher, ANNALS OF NUCLEAR ENERGY, v.120, pp.581 - 592, 2018-10

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