학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CFD ANALYSIS OF A VERY HIGH TEMPERATURE HELIUM HEATER IN THE VHTR SIMULATED EXPERIMENTAL LOOP | C. YOON, S. D. HONG, J. M. NOH, Y. W. KIM, AND J. H. CHANG(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | APPLICATION OF THE MARS/CANDU CODE TO SAFETY ANALYSES OF THE WOLSONG NPPS | C. YOON AND B. D. CHUNG(KAERI) S. H. AHN AND M. W. KIM(KINS) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | APPLICATION OF THE RETRAN SAFETY ANALYSIS MODEL TO INCREASE THE SAFETY MARGIN DURING OVERPRESSURE TRANSIENTS | JONG-GWAN YOO AND TAE-HWA HONG(KHNP) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | PREPARATION OF INPUT DECK USING MULTID COMPONENT TO MODEL 3-DIMENSIONAL REACTOR PRESSURE VESSEL FOR KORI 2 | DOOHYUK KANG AND JAESEUNG SUH(ENESYS) SEUNGHOON AHN AND YONGJIN CHO(KINS) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | ANALYTICAL VALIDATION OF THE HEAT CONDUCTION MODEL OF THE CORE HEAT TRANSFER MODEL IN THE TASS/SMR | SEONG WOOK LEE, HEE CHEOL KIM, YOUNG JONG CHUNG, AND KYOO HWAN BAE(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | COMPARISON BETWEEN HYDRODYNAMIC FORCES DERIVED FROM A FORCE-BALANCED METHOD AND A MOMENTUM-BALANCED METHOD | DONG KEON KIM, HYUNG SEOK KIM, AND WON TAE KIM(ENESYS) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | TEMPERATURE BEHAVIOR OF TRANSMITTER ROOM OF HWR FOR THE ACCIDENT CONDITIONS OF THE LOSS OF COOLANT IN THE PRIMARY CIRCUIT | SEYUN KIM, DONG HYUK LEE, AND JAE YONG LEE(KEPRI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A COMPARATIVE ANALYSIS FOR CONTROL ROD DROP ACCIDENT IN RETRAN DNB AND CETOP DNB MODEL | CHANG-KEUN YANG, YO-HAN KIM, AND SANG-JUN HA(KEPRI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 3D FLOW FIELD IN HOLD-UP VOLUME TANK OF ADVANCED PRESSURIZED REACTOR 1400 | T. W. KIM, Y. S. BANG, B. G. HUH, AND S. W. WOO(KINS) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | VALIDATION OF THE FUEL HEAT TRANSFER MODEL OF THE TASS-SMR CODE WITH THE EXPERIMENTAL DATA | SEONG WOOK LEE, SOO HYUNG KIM, YOUNG JONG CHUNG, AND KYOO HWAN BAE(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | SIMPLIFICATION OF MATRA CODE INPUT PARAMETERS AND DEVELOPMENT OF MATRA GUI | JEONG-HUN CHA, KYONG-WON SEO, HYUK KWON, BYUNG-MARN KOH, AND DAE-HYUN HWANG(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | SIMULATION OF RD-14M SMALL BREAK LOCA EXPERIMENTS BY CATHENA CODE | HYOUNG TAE KIM, JOO HWAN PARK, AND SANG BAIK KIM(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | COMPARISON OF FUEL TEMPERATURE CHARACTERISTICS BETWEEN STANDARD 37-ELEMENT AND CANFLEXFUEL BUNDLES | JUN HO BAE, YONGHEE KIM, GYUHONG ROH, AND JOO-HWAN PARK(KAERI) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | MODIFICATION AND VALIDATION OF THE MARS REFLOOD MODEL USING FLECHT-SEASET 31504 TEST | DONG GU KANG, SEUNG HOON AHN, AND YONG JIN CHO(KINS) TONG SOO CHOI(KNF) | PDF보기 | - | ||
| 2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | DEVELOPMENT OF CFD ANALYSIS METHODOLOGY OF HYDRAULIC LOAD EVALUATION IN POSRV PIPING SYSTEM | TAE-HYEON. KIM, JONG-PIL. PARK, WON-TAE. KIM, AND BYUNG-SUB. HAN(ENESYS) YOUNG-JO. CHOI(KHNP) | PDF보기 | - |
Last Modified : 1998-Autumn
