학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2017-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 11:20 | 컨벤션 A (B1F) | Pre/Post Processing for Thermal-Hydraulic Codes using the SALOME Platform | Sang Yong Lee(KINGS) and Chan Eok Park(KEPCO E&C) | PDF보기 | - |
| 2017-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 11:40 | 컨벤션 A (B1F) | ?Design Study on Mixing Performance of Rotational Vanes in Subchannel with Fuel Rod Bundles | Haneol Park(UNIST) and Incheol Bang(UNIST) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:00 | 컨벤션 A (B1F) | A Study on System Integrity during LOCV with Delayed Scram Event | Sangseob Lee(KEPCO E&C), Minsoo Park(KEPCO E&C), Jaeyoung Huh(KEPCO E&C), and Gyucheon Lee(KEPCO E&C) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:20 | 컨벤션 A (B1F) | Evaluation of the Integrity of Containment Pressure Boundary at Wolsong Unit 1?during a LOCA | Sungdeok Yi(NESS), Seoung Rae Kim(NESS), Un-sik Seo(KHNP), Dae-il Kwak(KHNP), Eunkyung Jang(NESS), and Keesoo Han(NESS) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:40 | 컨벤션 A (B1F) | Assessment of Prediction Capability of MARS-KS Code for Convection Heat Transfer from Horizontal Tube in Crossflow | Seong-Su Jeon(FNC Tech.), Gu-Won Kwon(FNC Tech.), Soon-Joon Hong(FNC Tech.), Sung-Won Bae(KAERI), and Tae-Soon Kwon(KAERI) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 10:00 | 컨벤션 A (B1F) | Comparative Study for Spacer Grid Models of TRACE and RELAP5 in FLECHT-SEASET Reflood Test | Byung Gil Huh(KAERI), Young Seok Bang(KAERI), and Chae-Yong Yang(KAERI) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 10:20 | 컨벤션 A (B1F) | Modification of Condensation Heat Transfer Model for the MARS Code in the Presence of Noncondensable Gases | Jun Yeob Lee(PNU), Jee Min Yoo(PNU), Byong Jo Yun(PNU), and Jae Jun Jeong(PNU) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 11:00 | 컨벤션 A (B1F) | Improvement of the subcooled boiling model in MARS for low-pressure conditions | Taewook Ha(PNU), Byongjo Yoon(PNU), and Jaejun Jeong(PNU) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 11:20 | 컨벤션 A (B1F) | Methodology for Thermal Analysis of Spent Fuel Dry Storage Cask Design?using MARS Code | Kyung Mo Kim(UNIST), Yeong Shin Jeong(UNIST), and In Cheol Bang(UNIST) | PDF보기 | - |
| 2017-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 11:40 | 컨벤션 A (B1F) | Parametric Analysis of Various Condensation Models Applicable for Passive Containment Cooling System | Yeon Jun Choo(FNC Tech.) | PDF보기 | - |
| 2017-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:00 | 컨벤션 B (B1F) | Experimental Study of Pool Quenching with Zircaloy and CrAl-Coated Claddings | Kwan Geun Lee(UST), Wang Kee In(KAERI), Seung Ho Ryu(UST), Ji Hyun Sohn(UST), and Chang Hwan Shin(KAERI) | PDF보기 | - |
| 2017-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:20 | 컨벤션 B (B1F) | Quenching experiments on various thermal properties under saturated and subcooled water condition with high-speed visualization | Tong Kyun Kim(POSTECH), Jun-young Kang(KAERI), Gi Cheol Lee(POSTECH), Hyunwoo Noh(POSTECH), Moo Hwan Kim(POSTECH), and Hyun Sun Park(POSTECH) | PDF보기 | - |
| 2017-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 09:40 | 컨벤션 B (B1F) | Analyses of Reflood Experimental results with 3x3 Deformed and Intact rod bundle | Seung-Hyun Hong(KAERI), Jongrok Kim(KAERI), Jong-Kuk Park(KAERI), Young-Jung Youn(KAERI), Hae Seob Choi(KAERI), and Sang-Ki Moon(KAERI) | PDF보기 | - |
| 2017-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 10:00 | 컨벤션 B (B1F) | Design of Fuel Assembly Tube for Flow Distribution Facility of PGSFR | Jinseok Hwang(FNC Tech.), Jiseok Kim(FNC Tech.), and Soonjoon Hong(FNC Tech.) | PDF보기 | - |
| 2017-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.27(Fri) 10:20 | 컨벤션 B (B1F) | Experimental Study on Heat Transfer Characteristics of a Multi-Pod Heat Pipe for Passive Cooling of Spent Fuel Pool | Changhwan Lim(KHU) and Hyungdae Kim(KHU) | PDF보기 | - |
Last Modified : 1998-Autumn
