Study of thermal hydraulic behaviors during steam generator multiple tube rupture events in PWR
- 1. Tokyo City University, Tokyo (Japan)
Description
Since the occurrence probability of multiple steam generator tube rupture (MSGTR) in PWR is low, analytical or experimental investigation for termination of such accidents is not performed explicitly. Therefore, thermal-hydraulic analysis of the plant behavior under the MSGTR (10 and 50 tubes) in all loops or in a single loop with station black out (SBO) were made in this study with use of the code RETRAN3D, and investigations for accident management (AM) of such accidents were made in order to contribute to continuous risk reduction efforts in the future. This study indicated that the water supply function to the SG is quite important for coping with accidents involving MSGTR accompanied by SBO to prevent core damage. Further, if the auxiliary feed water system loses its function, the time to reach the core exposure is predicted to be reduced by 1 hour or more in a MSGTR case as compared to a single-tube SGTR case. Therefore, in order to prevent the core damage during MSGTR, it is desirable to have alternative water injection equipment operable to quickly replace auxiliary feed water system if it fails and to increase the reliability of the auxiliary feed water system. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
- Imprint Pagination
- 2846 p.
- Journal Page Range
- 12 p.
Conference
- Title
- 10. international topical meeting on nuclear thermal hydraulics, operation and safety
- Acronym
- NUTHOS-10
- Dates
- 14-18 Dec 2014
- Place
- Ginowan, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47072657
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; ECCS; FEEDWATER; OUTAGES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; RUPTURES; STEAM GENERATORS; THERMAL HYDRAULICS; TUBES
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1084pdf; 12 refs., 29 figs., 2 tabs.