Reliability enhancement of APR + diverse protection system regarding common cause failures

Conference · Sun Jul 01 04:00:00 EDT 2012

OSTI ID:22105950

Oh, Y. G.; Kim, Y. M.; Yim, H. S. ^[1]; Lee, S. J. ^[2]

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1. KEPCO Engineering and Construction Company, Inc., 1045 Daedeok-Daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)
2. Chungnam National Univ., 99 Daehak-ro, Yuseong-gu, Daejeon 305-764 (Korea, Republic of)

The Advanced Power Reactor Plus (APR +) nuclear power plant design has been developed on the basis of the APR1400 (Advanced Power Reactor 1400 MWe) to further enhance safety and economics. For the mitigation of Anticipated Transients Without Scram (ATWS) as well as Common Cause Failures (CCF) within the Plant Protection System (PPS) and the Emergency Safety Feature - Component Control System (ESF-CCS), several design improvement features have been implemented for the Diverse Protection System (DPS) of the APR + plant. As compared to the APR1400 DPS design, the APR + DPS has been designed to provide the Safety Injection Actuation Signal (SIAS) considering a large break LOCA accident concurrent with the CCF. Additionally several design improvement features, such as channel structure with redundant processing modules, and changes of system communication methods and auto-system test methods, are introduced to enhance the functional reliability of the DPS. Therefore, it is expected that the APR + DPS can provide an enhanced safety and reliability regarding possible CCF in the safety-grade I and C systems as well as the DPS itself. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22105950
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
DESIGN
ECONOMICS
FAILURES
LOSS OF COOLANT
MITIGATION
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR SAFETY
RELIABILITY
SAFETY INJECTION
SIGNALS