Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Subject critical heat flux

Showing results 1 to 16 of 16

1
A procedure to predict subcooled-water-flow-boiling CHF in uniformly heated tubes for high-heat-flux applications

Kwon, YM; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.130, no.3, pp.310 - 328, 2000-06

2
(A) CHF mapping method based on dry spot model for finned surfaces = 드라이-스팟 모델에 기반한 핀 구조표면의 임계열유속 매핑법 개발link

Choi, Jin-Young; 최진영; et al, 한국과학기술원, 2016

3
(A) study on the effect of the twisted tape on CHF enhancement in a circular tube with R-134a = R-134a를 이용한 원형관에서 비틀림 테잎이 임계열유속 증진에 미치는 영향에 관한 연구link

Park, Jae-hwan; 박재환; et al, 한국과학기술원, 2008

4
(A) study on the flow induced vibration in two phase flow under heating and non-heating conditions = 가열 및 비가열 조건에서 이상유동의 유동기인진동에 대한 연구link

Kim, Dae-Hun; 김대헌; et al, 한국과학기술원, 2007

5
(A) unified modeling and experimental study of critical heat flux in flow boiling = 유동 비등에서 임계 열유속에 대한 통합 예측 모델 개발 및 실험적 연구link

Kim, Hong-Chae; 김홍채; et al, 한국과학기술원, 2002

6
Critical heat flux and onset of nucleate boiling tests in a finned rod bundle

Chae, HT; Park, JH; Kim, H; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12

7
Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11

8
Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes

Kim, CH; Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.14, pp.2868 - 2877, 2005-07

9
Development of a critical heat flux mapping method for fin-structured surfaces

Choi, Jin Young; No, Hee-Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.9, pp.1321 - 1331, 2016

10
Development of thermal hydraulic analysis code for nuclear reactors with annular fuels and assessment of the KAIST DNB-type theoretical critical heat flux model = Annular fuel이 장착된 원자로의 열수력 분석 코드 개발 및 KAIST의 DNB 영역의 이론적 임계열유속 모델 평가link

Han, Kyu-Hyun; 한규현; et al, 한국과학기술원, 2006

11
Enhancement of Boiling with Scalable Sandblasted Surfaces

Song, Youngsup; Wang, Chi; Preston, Daniel J.; Su, Guanyu; Rahman, Md Mahamudur; Cha, Hyeongyun; Seong, Jee Hyun; et al, ACS APPLIED MATERIALS & INTERFACES, v.14, no.7, pp.9788 - 9794, 2022-02

12
Experimental and numerical study on the chf performance of mixing vane = 혼합날개의 임계열유속 성능에 관한 실험적 연구와 수치해석link

Shin, Byung-Soo; 신병수; et al, 한국과학기술원, 2008

13
Experimental study of non-heating pool boiling simulation and CHF on reactor vessel wall = 수조 비등에 대한 비가열 모사 실험과 원자로용기 외벽에서의 임계열유속에 대한 실험적 연구link

Jeong, Yong-Hoon; 정용훈; et al, 한국과학기술원, 2003

14
Prediction of critical heat flux of saturated upward flow boiling water in vertical narrow rectangular channels = 얇은 수직 사각유로 상향유동에서의 포화비등조건 임계열유속 예측 연구link

Choi, Gil-Sik; 최길식; et al, 한국과학기술원, 2016

15
Vibration effects on critical heat flux in a vertical round tube = 수직 원형관에서 진동이 임계 열유속에 미치는 영향에 관한 연구link

Lee, Yong-Ho; 이용호; et al, 한국과학기술원, 2003

16
Visualization of a principle mechanism of critical heat flux in pool boiling

Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12

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