Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jeong, Yong-Hoon

Showing results 1 to 29 of 29

1
A Mechanistic Model to Predict the CHF on a Downward Facing Curved Surface

Park, Hae Min; Jeong, Yong-Hoon, The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), American Nuclear Society, 2014-12-15

2
(A) study on passive decay heat removal strategy and cost-benefit analysis of integrated passive safety system = 통합피동안전계통의 피동잔열제거전략과 비용-이득 분석에 관한 연구link

Kim, Sang-Ho; 김상호; et al, 한국과학기술원, 2016

3
(A) study on the correlations development for dryout heat flux in particle bed and film boiling heat transfer on spheres = 입자층의 건조 열유속 및 막비등 열전달 상관식 개발에 관한 연구link

Jeong, Yong-Hoon; 정용훈; et al, 한국과학기술원, 1998

4
An experimental study on CHF enhancement in flow boiling using Al2O3 nano-fluid

Kim, Tae-Il; Jeong, Yong-Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.53, no.5-6, pp.1015 - 1022, 2010-02

5
An investigation of pressure build-up effects due to check valve's closing characteristics using dynamic mesh techniques of CFD

Kim, Nam-Seok; Jeong, Yong-Hoon, ANNALS OF NUCLEAR ENERGY, v.152, pp.107996, 2021-03

6
(An) experimental study on pool boiling characteristics of carbon nano tube (CNT) and fullerene (C-60) nanofluids = 탄소 나노 튜브(CNT)와 풀러린(C-60) 나노유체의 수조 비등 특성에 관한 실험적 연구link

Ai, Melani; 아이, 멜라니; Chang, Soon-Heung; 장순흥; No, Hee-Cheon; 노희천; et al, 한국과학기술원, 2009

7
CFD verification for rod bundle under single phase flow condition = 단상 유동 조건하에서의 핵연료 봉 다발 CFD 검증link

Park, Sung-Kew; 박성규; et al, 한국과학기술원, 2014

8
CHF enhancement in flow boiling system with TSP and boric acid solutions under atmospheric pressure

Lee, Juno; Jeong, Yong-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3594 - 3600, 2010-10

9
CHF Study on Effect of Wettability under Pressurized Condition for Downward Facing Surface

Park, Hae Min; Jeong, Yong-Hoon, 2014 ANS Winter Meeting, American Nuclear Society, 2014-11-11

10
CHF, AGING EFFECT OF SiC SURFACES AND CHF OF Cr SURFACE UNDER ATMOSPHERIC CONDITION WITH SURFACE EVALUATIONS

Kam, Dong Hoon; Lee, Jong-Hyuk; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-17

11
Design of passive residual heat removal system for low temperature and low pressure pool-type lwr using two-phase closed thermosyphon = 열사이펀을 이용한 저온저압 수조형 경수로의 피동잔열제거계통 설계link

Moon, Jang-Sik; 문장식; et al, 한국과학기술원, 2014

12
Development of once-through hybrid sulfur process for nuclear hydrogen production = 원자력수소생산을 위한 Once-through형 하이브리드 황 공정의 개발link

Jung, Yong-Hun; 정용훈; et al, 한국과학기술원, 2010

13
Effect of Eddy on CHF Characteristics with Suddenly Expanded Flow Channel

KIM, YONG JIN; Song, Sub Lee; 문상기; Chang, Soon-Heung; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-18

14
Effect of heater material and coolant additives on CHF for a downward facing curved surface

Park, Hae Min; Jeong, Yong-Hoon; Heo, Sun, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.344 - 351, 2014-10

15
Effect of Pressure on Critical Heat Flux on the Top of the Reactor Vessel Lower Head

Park, Hae Min; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-17

16
Engineering design and analysis for new moderated space propulsion reactors utilizing advanced HEU and LEU fuels = 고성능 HEU 및 LEU 핵연료들을 이용한 신형 우주추진용 감속원자로 공학 설계 및 해석link

Nam, Seung-Hyun; 남승현; Jeong, Yong-Hoon; 정용훈; et al, 한국과학기술원, 2016

17
Experimental CHF study for the top of the reactor vessel lower head = 원자로용기 하부헤드 상부에서의 임계열유속에 관한 실험적 연구link

Park, Hae-Min; 박해민; et al, 한국과학기술원, 2014

18
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

19
Experimental study on flow boiling CHF characteristics for Fe3O4-water nanofluid = Fe3O4 나노유체의 유동비등 임계열유속 특성에 관한 실험적 연구link

Lee, Tae-Seung; 이태승; et al, 한국과학기술원, 2013

20
Experimental study on the pool boiling CHF enhancement using magnetite-water nanofluids

Lee, Jong-Hyuk; Lee, Tae-Seung; Jeong, Yong-Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.55, no.9-10, pp.2656 - 2663, 2012-04

21
Flow boiling critical heat flux characteristics of magnetic nanofluid at atmospheric pressure and low mass flux conditions

Lee, Tae-Seung; Lee, Jong-Hyuk; Jeong, Yong-Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.56, no.1-2, pp.101 - 106, 2013-01

22
Improvement of supercritical $CO_2$ brayton cycle using binary gas mixture = 이성분계 혼합가스를 이용한 초임계 이산화탄소 브레이튼 사이클 개선에 관한 연구link

Jeong, Woo-Seok; 정우석; et al, 한국과학기술원, 2011

23
Improvement of supercritical $CO_2$ brayton cycle using binary gas mixture = 이성분계 혼합가스를 이용한 초임계 이산화탄소 브레이튼 사이클 개선에 관한 연구link

Jeong, Woo-Seok; 정우석; et al, 한국과학기술원, 2011

24
LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS

Lee, Je-Whan; Jeong, Yong-Hoon; Chang, Yoon-Il; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.43, no.4, pp.383 - 390, 2011-08

25
Passive Coping Strategy with Integrated Passive Safety System (IPSS) for Various LOCAS in SBO

Kim, Sang Ho; HAM, JAEHYUN; Chang, Soon-Heung; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-18

26
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

27
RANS Simulation of Turbulent Swept Flow Over a Wire in a Channel for Core Thermal Hydraulic Design

You, Byung-Hyun; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-19

28
The effect of pressure on the critical heat flux in water-based nanofluids containing Al2O3 and Fe3O4 nanoparticles

Lee, Jong-Hyuk; Lee, Tae-Seung; Jeong, Yong-Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.61, pp.432 - 438, 2013-06

29
The effects of pressure and nanofluid stability on pool boiling CHF using magnetite-water nanofluids = 자성유체의 임계열유속에 대한 압력 및 분산효과 연구link

Lee, Jong-Hyuk; 이종혁; et al, 한국과학기술원, 2013

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