Published May 2017 | Version v1
Miscellaneous

Beyond-design-basis Accident Analysis using Bayesian Network: Application to Research Reactor

  • 1. Korea Atomic Energy Research Institute, Daejeon(Korea, Republic of)

Description

The research reactor can be subjected to an internal accident during the design lifetime. Especially, a loss of primary coolant system (LOPCS) flow is one of significant threats to the safety of pool-type research reactor. This failure is possibly extended to the direct core damage (CD) of the reactor. Under this background, the objective of this paper is to perform the beyond-design basis accident analysis based on a Bayesian network (BN) instead of utilizing the standard fault tree (FT) analysis. For this purpose, the BN for LOPCS leading to the CD is developed based on an event tree (ET) and fault trees (FTs) related to the LOPCS. Then, the BN analysis is conducted under an assumption that the CD accident occurs. The analysis results reveal the updated risks of all events, and the most vulnerable scenarios and basic events. Finally, the BN is expected to be utilized for identifying the real-time risk status and to aid in making risk-informed decisions. This study focuses on the beyond-design-basis accident analysis of LOPCS of research reactor. The concept of a BN is applied for probabilistic safety assessment method instead of utilizing the standard FT analysis for a systems analysis. Unlike the standard FT analysis, the BN enables an analyst to explore scenarios subjected to beyond-design-basis accident. This is because the Bayesian inference facilitates the updating of prior probability information about all events based on the evidence. The numerical result shows that the BN finally assists in the identification of important events that lie on an updated critical path.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Spring Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050038
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING SYSTEMS; DAMAGE; DECISION MAKING; DESIGN; FAILURES; HAZARDS; PROBABILITY; RESEARCH REACTORS; SAFETY; SAFETY ANALYSIS; USES
Descriptors DEC
ENERGY SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Notes
4 refs, 4 figs, 1 tab