Seismic Response Amplification Factors of Nuclear Power Plants for Seismic Performance Evaluation of Structures and Equipment due to High-frequency Earthquakes

2020 ◽  
Vol 24 (3) ◽  
pp. 123-128
Author(s):  
Seung-Hyun Eem ◽  
◽  
In-Kil Choi ◽  
Jeon Bub-Gyu ◽  
Shinyoung Kwag
Keyword(s):  
Performance Evaluation ◽  
Seismic Response ◽  
Seismic Performance ◽  
High Frequency ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Amplification Factors ◽  
Seismic Performance Evaluation ◽  
Response Amplification

A Critical Comparison of Seismic Qualification Requirements for Safety Equipment in Various Codes and Standards

2003 ◽  
Author(s):  
F. G. Abatt ◽  
Quazi Hossain ◽  
Milon Meyer
Keyword(s):  
Seismic Performance ◽  
Seismic Design ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Lower Class ◽  
Department Of Energy ◽  
Building Structures ◽  
Performance Category ◽  
Code Provisions

Evaluation of life safety risks to facility occupants, public, and the environment that may result from earthquake events involves both building structures and equipment supported from these structures. But, it is the seismic design of building structures that typically receive the bulk of the attention from the code committees of the national professional organizations and the regulatory authorities. For safety related equipment in nuclear facilities (e.g., Seismic Category I equipment in nuclear power plants and Seismic Performance Category 3 and 4 equipment in the Department of Energy facilities), the seismic design and analysis guidelines and acceptance criteria are well established. But, for Nonseismic Category equipment in nuclear power plants and Seismic Performance Category 1 and 2 equipment in Department of Energy facilities, these have not yet been developed to the same level of completeness and rigor. The code provisions and guidelines available today for these lower class/categories of equipment are briefly, but critically discussed here, along with a comparison of the results of the application of these code provisions.

Seismic response of base isolated nuclear power plants considering impact to moat walls

2018 ◽  
Vol 328 ◽  
pp. 58-72 ◽  
Author(s):  
A. Sarebanha ◽  
G. Mosqueda ◽  
M.K. Kim ◽  
J.H. Kim
Keyword(s):  
Seismic Response ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants

Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and Information

2009 ◽  
Author(s):  
Tadahisa Nagata ◽  
Ken-ichiro Sugiyama
Keyword(s):  
Performance Evaluation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Annual Report ◽  
Open Data ◽  
Plant Performance ◽  
Failure Type ◽  
Early Infant ◽  
Early Failures

The operation term of Japanese nuclear power plants is less than 13 months. Moreover, the refuel outage period is longer than the other countries. It is likely that excessive preventive maintenances result in early “infant mortality” failures (early failures). However, the statistical evaluation report about failure type of Japanese nuclear power plants was not found. Therefore, Evaluation of plant engineering performance was tried on open data/information with a statistical method. The Weibull distribution/analysis, which needs not only failure data but also censored data like the preventive maintenance, was applied to plant performance evaluation. As open data/information, an annual report; “Operational Status of Nuclear Facilities in Japan” is very popular for the operation database of Japanese nuclear power plants. However, maintenance date/information of failed equipment which caused plant shutdowns were not reported in this annual report. Therefore, every equipment was assumed to be maintained during every shutdown, because this assumption generally makes conservative results of failure rate and Mean Time Before Failure (MTBF) for discussion about early failures. Data till March 2007 were collected from these annual reports. As a result of plant performance evaluation, failure type was early “infant mortality” failure type. Excessive maintenances probably resulted in early failure type. Moreover, influence of early failures and effects of plant design modifications were evaluated. Almost 30% of failures occurred within one month after restart, and failure type excluded these failures was chance (random) type. Early failures within one month may be closely evaluated to improve maintenances. Design modification effect of Japanese nuclear power plants was confirmed.

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