Study on the PWR Steam Generator Behavior with improved steam-driven aux feedwater system under prolonged SBO Accident
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The only available passive decay heat removal system of current PWRs is a turbine-driven auxiliary steam generator (SG) feedwater (TD-AFW) system. If a SG water level becomes too high, however, turbine blades could be damaged due to a large amount of becomes too high, however, turbine blades could be damaged due to a large amount of moisture in steam and the SG cooling capability would not be maintained any longer. Therefore, the SG water level should be controlled to prevent the turbine from being damaged during a Station Black-Out (SBO) accident. In this paper, an improved design feature is proposed to provide electric power for controlling SG water level when both off-site power and the emergency diesel generators are not available. There are additional SG level gauges and valve controllers to control the steam flow into the auxiliary turbine in an improved TD-AFW system. Electric power for this control system is provided by a small additional generator which is connected to the existing auxiliary turbine shaft. Using this new feature, decay heat cooling is available for 29 hours with only 1 condensate storage tank which is the water source of the AFW. Eventually, it is concluded that the improved TD-AFW system with an additional SG level controller and generator can avoid an early SG full level and continue long term cooling during a prolonged SBO accident
Additional details
Publishing Information
- Publisher
- Pacific Nuclear Council
- Imprint Place
- La Grange Park (United States)
- Imprint Title
- Proceedings of the 18th Pacific Basin Nuclear Conference
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [7 p.]
Conference
- Title
- 18. Pacific Basin Nuclear Conference
- Acronym
- PBNC 2012
- Dates
- 18-23 Mar 2012
- Place
- Busan (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45032777
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTROL; DAMAGE; DESIGN; FEEDWATER; PWR TYPE REACTORS; REACTOR ACCIDENTS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; REMOVAL; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs, 4 figs, 1 tab