Published March 2012 | Version v1
Miscellaneous

Study on the PWR Steam Generator Behavior with improved steam-driven aux feedwater system under prolonged SBO Accident

  • 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

Part of:
Proceedings of the 18th Pacific Basin Nuclear Conference

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