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) | 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 | - | ||
2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | ANALYSIS OF THE NATURAL CIRCULATION CHARACTERISTICS IN THE PRIMARY LOOP OF THE VISTA FACILITY FOR SMART BY USING THE MARS CODE | HYUN-SIK PARK, KI-YONG CHOI, SEOK CHO, SUNG-JAE YI, CHOON-KYUNG PARK, AND MOON-KI CHUNG(KAERI) | PDF보기 | - | ||
2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | PRE-TEST CALCULATION OF PKL III G3.1 TEST | SEUNG WOOK LEE AND BUB DONG CHUNG(KAERI) | PDF보기 | - | ||
2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | PRELIMINARY ASSESSMENT OF THE INTERFACIAL SOURCE TERMS IN SPACE CODE | SUNWON BAE, JEONG WOO KIM, SU HYONG KIM, AND KYUNG DU KIM(KAERI) | PDF보기 | - | ||
2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | DRYOUT ON OUTER SPHERICAL VESSEL LOWER HEAD WITH STREAMLINED GAP | SANG W. NOH, KYOUNG M. KANG, AND KUNE Y. SUH(SNU) | PDF보기 | - | ||
2009-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | DEVELOPMENT OF THE ULCHIN 34 MELCOR1.8.6 MODEL FOR PHENOMENOLOGICAL UNCERTAINTY ANALYSIS IN LEVEL 2 PSA | GUNHYO JUNG AND JINYOUNG LEE(FNC) KWNGIL AHN AND SOOYONG PARK(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn