Fault-tree analysis of the EBR-II reactor shutdown system
Description
As part of level I Probabilistic Risk Assessment (PRA) of the Experimental Breeder Reactor II (EBR-II), detailed fault trees for the reactor shutdown system are developed. Two classes of transient events that are of particular importance to EBR-II operation and require reactor shutdown are loss of flow (LOF) and transient over power (TOP). Normally in these events, detection channels would automatically open a number of contacts in two redundant shutdown strings. The paper gives the probabilities of scram failure in case of an LOF or TOP. Fault-tree analysis of the EBR-II shutdown system has provided not only a systematic process for calculating the probabilities of system failures but also a useful means for understanding the system and how its components interact during transient events that require shutdown
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 403-404.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24016000
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALIBRATION; CONTROL ELEMENTS; EBR-2 REACTOR; ERRORS; FAULT TREE ANALYSIS; HUMAN FACTORS; LOSS OF FLOW; NEUTRON FLUX; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; RELIABILITY; RISK ASSESSMENT; SCRAM; SCRAM RODS; TRANSIENT OVERPOWER ACCIDENTS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; OPERATION; PERSONNEL; POWER REACTORS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SHUTDOWN; SODIUM COOLED REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Secondary number(s)
- CONF-911107--.