1 |
Y. Naito, A. Niousha, Analytical study on system identification of fixed-base transfer functions for an embedded reactor building, in: SMiRT-18,August 7-12, 2005.
|
2 |
A. Onouchi, A. Niousha, Y. Naito, M. Kan, Y. Mihara, Forced vibration test of an ABWR nuclear reactor building -Data analysis and system identification, in: SMiRT-18, August 7-12, 2005.
|
3 |
A. Niousha, Y. Naito, E. Miyasaka, S. Uchiyama, Dynamic characteristics of a SC Building in Kashiwazaki NPP site using vibration test - Part 1: data analysis and system identification, in: SMiRT-19,August, 2007.
|
4 |
Atomic Energy Council, Executive Yuan ROC, The Third Ten-Year Integrated Safety Assessment Report of KuoSheng Nuclear Power Plant, NRD-SER-101-12, 2012 (in Chinese).
|
5 |
D.-D. Nguyen, B. Thusa, T.-S. Han, T.-H. Lee, Identifying significant earthquake intensity measures for evaluating seismic damage and fragility of nuclear power plant structures, Nucl. Eng. Technol. 52 (1) (2020) 192-205, https://doi.org/10.1016/j.net.2019.06.013.
DOI
|
6 |
U.S. Nuclear Regulatory Commission, 10 CFR Part 100 - Reactor Site Criteria, USNRC, 2017.
|
7 |
USNRC, Restart of a Nuclear Power Plant Shut Down by a Seismic Event, Office of Nuclear Regulatory Research, Regulatory Guide RG 1, 1997, p. 167.
|
8 |
USNRC, Pre-earthquake Planning, Shutdown and Restart of a Nuclear Power Plant Following an Earthquake, Office of Nuclear Regulatory Research, 2016. Draft Regulatory Guide DG-1337 (Proposed Revision 1 to Regulatory Guide RG 1.166).
|
9 |
A. Niousha, Y. Naito, M. Kan, A. Onouchi, A. Tachibana, System identification of a nuclear reactor building under fixed-base condition using measured data, in: SMiRT-18, August 7-12, 2005.
|
10 |
M.M. Hasan, J.K. Mayaka, J.C. Jung, Development of earthquake instrumentation for shutdown and restart criteria of the nuclear power plant using multivariable decision-making process, Nucl. Eng. Technol. 50 (6) (2018) 860-868, https://doi.org/10.1016/j.net.2018.04.004.
DOI
|
11 |
Guidelines for Structural Integrity Assessment for Nuclear Power Components Experienced Earthquake, JANTI-SANE-G1, JANTI-SANE-G2, Japan Nuclear Safety Institute, 2012 (in Japanese).
|
12 |
P. Caravani, M.L. Watson, W.T. Thomson, Recursive least-squares time domain identification of structural parameters, J. Appl. Mech., Trans. ASME 44 Ser E (1) (1977) 135-140.
|
13 |
American National Standards Institute (ANSI), ANSI/ANS-2.23, Nuclear Power Plant Response to an Earthquake, American Nuclear Society, IL, USA, 2002.
|
14 |
IAEA, Earthquake Preparedness and Response for Nuclear Power Plants, International Atomic Energy Agency, Vienna,, 2011. Safety Reports Series No. 66.
|
15 |
IAEA, On-line Monitoring for Improving Performance of Nuclear Power Plants, Part 1: Instrument Channel Monitoring, International Atomic Energy Agency, 2008.
|
16 |
IAEA, On-line Monitoring for Improving Performance of Nuclear Power Plants, Part 2: Process and Component Condition Monitoring and Diagnostics, International Atomic Energy Agency, 2008.
|
17 |
EPRI NP-6695, Guidelines for Nuclear Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 1989.
|
18 |
EPRI Report 30020007220, Guidelines for Nuclear Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 2013.
|
19 |
American National Standards Institute (ANSI), ANSI/ANS-2.23-2016, Nuclear Power Plant Response to an Earthquake, American Nuclear Society, IL, USA, 2016.
|
20 |
S.Y. Chu, S.C. Lo, Application of the on-line recursive least-squares method to perform structural damage assessment, Struct. Contr. Health Monit. 18 (3) (2011) 241-264, https://doi.org/10.1002/stc.362.
DOI
|
21 |
F. Lin, H. Li, Safety analysis of nuclear containment vessels subjected to strong earthquakes and subsequent tsunamis, Nucl. Eng. Technol. 49 (5) (2017) 1079-1089, https://doi.org/10.1016/j.net.2017.03.008.
DOI
|
22 |
EPRI Report 3002005284, Guidelines for Nuclear Power Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 2015.
|
23 |
USNRC, Pre-earthquake Planning and Immediate Nuclear Power Plant Operator Post-earthquake Actions, Office of Nuclear Regulatory Research, Regulatory Guide RG 1, 1997, p. 166.
|
24 |
IAEA, Safety Guide No. NS-G-1.6 - Seismic Design and Qualification for Nuclear Power Plants, International Atomic Energy Agency, 2003.
|
25 |
J.N. Juang, Applied System Identification, Prentice Hall, Englewood Cliffs, New Jersey, 1994.
|
26 |
J.W. Lin, R. Betti, A.W. Smyth, R.W. Longman, On-line identification of nonlinear hysteretic structural systems using a variable trace approach, Earthq. Eng. Struct. Dynam. 30 (9) (2001) 1279-1303, https://doi.org/10.1002/eqe.63.
DOI
|
27 |
S.Y. Chu, S.C. Lo, Application of real-time adaptive identification technique on damage detection and structural health monitoring, Struct. Contr. Health Monit. 16 (2) (2009) 154-177, https://doi.org/10.1002/stc.304.
DOI
|
28 |
P. Varpasuo, System identification of NPP reactor building on the basis of blast test responses, in: SMiRT-15, August 15-20, 1999.
|
29 |
J. Hur, E. Althoff, H. Sezen, R. Denning, T. Aldemir, Seismic assessment and performance of nonstructural components affected by structural modeling, Nucl. Eng. Technol. 49 (2) (2017) 387-394, https://doi.org/10.1016/j.net.2017.01.004.
DOI
|