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Results 1-10 of 33 (Search time: 0.004 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21

2
Conceptual Design of Additional Injection Tank for Heat Load Reduction on Reactor Vessel Lower Head during Severe Accident

Hu, Ji Young; Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10-25

3
Experimental Study on the Critical Heat Flux Characteristic of the Seawater

Park, Hae Min; Lee, Taeseung; Jeong, Yong Hoon, The 18th Pacific Basin Nuclear Conference(PBNC 2012), KAIF,KNS, 2012-05

4
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12

5
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17

6
Experimental CHf study on the scaling effect of 2-D slice test section for in-vessel retention through external reactor vessel cooling strategy

Park, Hae Min; Heo, Sun; Song, Chanyi; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02

7
The Effect of the Geometric Scale on the Critical Heat Flux for the Top of the Reactor Vessel Lower Head

Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2012-05-17

8
Effect of Geometry, Heater Material and Coolant Additives on CHF of Curved Inclined Surface

Park, Hae Min; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2012-09

9
Flow boiling critical heat flux enhancement on the 2-D slice for boric acid and TSP solution

Park, Hae Min; Heo, Sun; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25

10
Heat Load Reduction by Additional Injection Tank on Reactor Vessel Lower Head during Severe Accident

Park, Hae Min; Jeong, Yong Hoon, The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), KNS,CNS, 2011-10-10

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