Seismic capacity evaluation of a group of vertical U-tube heat exchanger with support frames for seismic PSA

Watanabe, Yuichi*; Muramatsu, Ken; Oikawa, Tetsukuni

Nuclear Engineering and Design, 235(23), p.2495 - 2512, 2005/12

https://doi.org/10.1016/j.nucengdes.2005.05.037

This paper presents an evaluation of seismic capacity of a group of vertical U-tube type heat exchangers(HXs) with support frames for residual heat removal systems of BWRs for seismic Probabilistic Safety Assessment in Japan. The median capacity was evaluated by a time history response analysis with a detailed model for a representative HX selected from four HXs. The logarithmic standard deviation(LSD) for uncertainty due to lack of knowledge was evaluated with consideration of the variabilities in three influential parameters, i.e., diameter of anchor bolt, weight of HX and position of center of gravity of HX. The dominant failure mode of HXs was the failure of anchor bolts of lugs mainly due to shearing stress. The capacity expressed in terms of zero period acceleration on the foundation of HX was evaluated to be 4,180 Gal(4.3 g) for median, LSD for uncertainty due to randomness was 0.11 from the variability in material property and LSD due to lack of knowledge was 0.21 to 0.53 depending on combination of the variability in design parameters to be considered.

A Procedure for the determination of scenario earthquakes for seismic design based on probabilistic seismic hazard analysis

Hirose, Jiro*; Muramatsu, Ken; Okumura, Toshihiko*; Taki, Satoshi*

JAERI-Research 2002-009, 220 Pages, 2002/03

JAERI-Research-2002-009.pdf:13.31MB

This report presents procedures for the determination of Scenario Earthquakes for seismic design based on Probabilistic Seismic Hazard Analysis (PSHA). Recently PSHA was recognized as an important basis to identify dominant earthquakes predicted to threaten the site in future. The identified earthquakes are called Probability-Based Scenario Earthquakes (PBSEs). The concept of PBSEs originates from the studies of US NRC and Ishikawa & Kameda. The objective of this study is to formulate the procedures to determine the PBSEs and, through this application, to demonstrate the feasibility of the application to seismic design. This report consists of three parts, namely, procedures to compile analytical conditions for PBSEs, an assessment to determine PBSEs for a model site using the Ishikawa's concept and examination of uncertainty involved in analytical conditions. The results imply that the procedures based on the Ishikawa's concept is a useful evaluation technique to determine scenario earthquakes for seismic design considering uncertainty involved in analytical conditions.

Probabilistic seismic stability analysis for the ground of quaternary deposits

Hirose, Jiro*; Muramatsu, Ken; Kanda, S.*; Tomishima, S.*; Takeda, Masatoshi*

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Research at JAERI for effective uses of seismic PSA

Muramatsu, Ken; Hirose, Jiro*; Oikawa, Tetsukuni; Kondo, Masaaki

Proceedings of 15th KAIF/JAERI Annual Meeting, p.229 - 238, 2000/00

no abstracts in English

Summary report of seismic PSA of BWR model plant

JAERI-Research 99-035, 314 Pages, 1999/05

JAERI-Research-99-035.pdf:14.99MB

no abstracts in English

Consideration of the effect of human error in a seismic PSA

Yokobayashi, Masao; ; Muramatsu, Ken

Probabilistic Safety Assessment and Management, 3, p.1901 - 1906, 1998/00

no abstracts in English

An Analysis of effect of correlation of response in the system reliability analysis in a seismic PSA of a nuclear power plant

Watanabe, Yuichi*; ; Muramatsu, Ken

20th CNS Nuclear Simulation Symposium, p.1 - 10, 1997/00

no abstracts in English

Estimation methodology for functional failure probability of reactor buildings under earthquake motion

; *; *; *

PSA95: Proc. of Probabilistic Safety Assessment Methodology and Applications, 2, p.715 - 720, 1995/00

no abstracts in English

Development of seismic PSA methodology at JAERI

Muramatsu, Ken; ; Matsumoto, Kiyoshi; ; Kondo, Masaaki; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1333 - 1340, 1995/00

no abstracts in English

SHEAT: A Computer code for probabilistic seismic hazard analysis, users manual

; *; *; Kondo, Masaaki; Abe, Kiyoharu

JAERI-Data/Code 94-009, 135 Pages, 1994/08

JAERI-Data-Code-94-009.pdf:4.05MB

no abstracts in English