Effects of Tube Rupture Modeling and Parameters on Analysis of MSGTR Event Progression in PWR
Creators
- 1. Dept of Environmental System, Cheonan College of Foreign Studies, Anseo-dong, Cheonan, Choongnam, 330-705 (Korea, Republic of)
- 2. Thermal-Hydraulic Safety Research Team, Korea Atomic Energy Research Institute, Deogjin-dong, Yusong-gu, Daejeon, 305-353 (Korea, Republic of)
- 3. Dept of Mechanical Engineering, Sunmoon University, Tangjeong-myeon, Asan, Choongnam, 336-708 (Korea, Republic of)
Description
A multiple steam generator tube rupture (MSGTR) event in APR1400 has been investigated using the best estimate thermal hydraulic system code, MARS1.4. The effects of parameters such as the number of ruptured tubes, rupture location, affected steam generator on analysis of the MSGTR event in APR1400 is examined. In particular, tube rupture modeling methods, single tube modeling (STM) and double tube modeling (DTM), are compared. When five tubes are ruptured, the STM predicts the operator response time of 2085 seconds before main steam safety valves (MSSVs) are lifted. The effects of rupture location on the MSSV lift time is not significant in case of STM, but the MSSV lift time for tube-top rupture is found to be 25.3% larger than that for rupture at hog-leg side tube sheet in case of DTM. The MSSV lift time for the cases that both steam generators are affected (4C5x, 4C23x) are found to be larger than that of the single steam generator cases (4A5x, 4B5x) due to a bifurcation of the primary leak flow. The discharge coefficient of Cd is found to affect the MSSV lift time only for smaller value of 0.5. It is found that the most dominant parameter governing the MSSV lift time is the leak flow rate. Whether any modeling method is used, it gives the similar MSSV lift time if the leak flow rate is close, except the case of both steam generators are affected. Therefore, the system performance and the MSSV lift time of the APR1400 are strongly dependent on the break flow model used in the best estimate system code. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-663-2
- Imprint Pagination
- 10 p.
Conference
- Title
- 2002 International congress on advances in nuclear power plants
- Acronym
- ICAPP'02
- Dates
- 9-13 Jun 2002
- Place
- Hollywood, FL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 40044566
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW MODELS; FLOW RATE; LEAKS; PWR TYPE REACTORS; RELIEF VALVES; RUPTURES; SCANNING TUNNELING MICROSCOPY; SIMULATION; STEAM GENERATORS; THERMAL HYDRAULICS; TUBES
- Descriptors DEC
- BOILERS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FAILURES; FLOW REGULATORS; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; MICROSCOPY; POWER REACTORS; REACTORS; THERMAL REACTORS; VALVES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.