Published November 14, 2007 | Version v1
Report

Development of Seismic PSA Methodology Considering Aftershock

  • 1. Japan Nuclear Energy Safety Organization (JNES), Kamiya-cho MT Bldg, 4-3-20 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

Description

When a large earthquake (main shock) has occurred around nuclear power plant, it is generally followed by a number of large aftershocks. Therefore, the safety of power plant against the main shock and aftershocks should be assessed. We have been developed the following seismic PSA methodology for nuclear power plant considering large aftershocks: 1) Seismic hazard analysis of aftershocks: It is possible to predict the aftershock activity by combining the evaluating the number of aftershock following main shock and the frequency of aftershock of a certain magnitude. The seismic motions due to aftershocks are evaluated by attenuation formula or fault model considering the spatial distribution of aftershocks in the aftershock region. 2) Seismic fragility evaluation: Structures and components fragility can be evaluated by considering seismic motions due to main shock and aftershocks that will occur within a short period of time. 3) System reliability analysis: The system reliability analysis of a nuclear power plant is taken into account for additional accidents by aftershocks while the reactor is establish cold shutdown after scram by a main shock. This paper is organized in two sections. In the first section, the seismic PSA methodology for aftershock is explained. In the second section, an example of the seismic hazard analysis for aftershock based on earthquake observation records is presented. In this analysis the prediction model of aftershock activity were verified and the influence of the seismic hazard of the aftershock was also examined by comparing with seismic hazard of the main shock. (authors)

Part of:
Proceedings of the Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities

Additional details

Publishing Information

Imprint Title
Proceedings of the Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities
Imprint Pagination
336 p.
Journal Page Range
p. 165-174
Report number
NEA-CSNI-R--2007-14

Conference

Title
Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities
Dates
6-8 Nov 2006
Place
Jeju Island (Korea, Republic of)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39091000
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S58: GEOSCIENCES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; AFTERSHOCKS; ATTENUATION; EARTHQUAKES; EVALUATION; FORECASTING; HAZARDS; NUCLEAR POWER PLANTS; RELIABILITY; SAFETY; SCRAM; SPATIAL DISTRIBUTION
Descriptors DEC
DISTRIBUTION; NUCLEAR FACILITIES; POWER PLANTS; REACTOR SHUTDOWN; SEISMIC EVENTS; SHUTDOWN; THERMAL POWER PLANTS

Optional Information

Notes
5 refs.