Experimental study of Siphon breaker about size effect in real scale reactor design
Conference
·
OSTI ID:22106058
- Mechanical Engineering Dept., POSTECH, Pohang, 790-784 (Korea, Republic of)
- Div. of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784 (Korea, Republic of)
- Dept. of Nuclear Engineering, Hanyang Univ., Seoul, 133-791 (Korea, Republic of)
- KAERI, Yuseong, Daejeon, 305-353 (Korea, Republic of)
Rupture accident within the pipe of a nuclear reactor is one of the main causes of a loss of coolant accident (LOCA). Siphon-breaking is a passive method that can prevent a LOCA. In this study, either a line or a hole is used as a siphon-breaker, and the effect of various parameters, such as the siphon-breaker size, pipe rupture point, pipe rupture size, and the presence of an orifice, are investigated using an experimental facility similar in size to a full-scale reactor. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22106058
- Resource Relation:
- Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 4 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS
Estimation of LOCA break size using cascaded support vector regression - 334
CULSETS, a faster-than-real-time transient simulator code for application to the small-break LOCA
Technical Report
·
Mon Jun 16 00:00:00 EDT 2003
·
OSTI ID:22106058
+2 more
Estimation of LOCA break size using cascaded support vector regression - 334
Conference
·
Thu Jun 15 00:00:00 EDT 2017
·
OSTI ID:22106058
CULSETS, a faster-than-real-time transient simulator code for application to the small-break LOCA
Conference
·
Thu Jan 01 00:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:22106058