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Results 1-10 of 11 (Search time: 0.01 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Flow boiling CHF experiment with sudden expansion tubes

Kim, Yong Jin; Song, Sub Lee; Moon, Sang-Ki; Chang, Soon Heung; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.114, 2020-05

2
An experimental observation of the effects of submicron- and micron-sized mesoporous silica particles on the critical heat flux

Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.160, pp.120182, 2020-10

3
A novel approach for critical heat flux enhancement during severe accident mitigation with removal of radioactive materials from the coolant

Kam, Dong Hoon; Jeong, Yong Hoon; Choi, Sung-Min; Yun, Jong-Il; Lee, Jong Hyuk; Lee, Taeseung; Lee, Min Suk; Jung, Il-Kwon; Jang, Jin-Wook; Sihn, Youngho; Kim, Tae-Hyeong; Lee, Jun-Ki; Kang, Shin-Hyun; Han, Sol-Chan; Lee, Jun-Yeop; Jee, Young Taek, NUCLEAR ENGINEERING AND DESIGN, v.365, pp.110715 - 110725, 2020-08

4
Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe

Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; Son, In Woo; Kim, Yonghee; Lee, Jeong-Ik; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, 2020-12

5
Correction factor development for the 2006 Groeneveld CHF look-up table for rectangular channels under low pressure

Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, pp.110869, 2020-12

6
The importance of representative aerosol diameter and bubble size distribution in pool scrubbing

Kim, Yo Han; Kam, Dong Hoon; Yoon, Jongwoong; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.147, 2020-11

7
Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.136, 2020-02

8
Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident

Lee, Seongmin; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.6, pp.1110 - 1119, 2020-06

9
Design Of Air-Cooled Waste Heat Removal System With String Type Direct Contact Heat Exchanger And Investigation Of Oil Film Instability

Moon, Jangsik; Jeong, Yong Hoon; Addad, Yacine, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.4, pp.734 - 741, 2020-04

10
A heat transfer model development for CHF prediction with consideration of dry patch characteristics

Kam, Dong Hoon; Jeong, Yong Hoon; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.148, 2020-02

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