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Journal Articles

Development of failure mitigation technologies for improving resilience of nuclear structures, 6; Resilience improvements of fast reactors by failure mitigation for excessive earthquake

Yamano, Hidemasa; Futagami, Satoshi; Ando, Masanori; Kurisaka, Kenichi

Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 11 Pages, 2024/03

In this study, the dynamic structural analysis of the reactor vessel for excessive earthquake using the FINAS/STAR code has shown the elephant foot buckling deformation and calculated the cumulative fatigue failure fraction. Using the calculation results, this paper describes the fragility curve using the safety factor method, indicating the significantly improved curve compared the previous one.

Journal Articles

Development of failure mitigation technologies for improving resilience of nuclear structures, 1; Failure mitigation by passive safety structures without catastrophic failure

Kasahara, Naoto*; Yamano, Hidemasa; Nakamura, Izumi*; Demachi, Kazuyuki*; Sato, Takuya*; Ichimiya, Masakazu*

Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 8 Pages, 2024/03

In this study, we propose failure mitigation methods by application of passive safety structures. The idea of the passive safety structures was applied to next generation fast reactors under high temperature conditions and excessive earthquake conditions.

Journal Articles

Fundamental study on seismic safety margin for seismic isolated structure using the laminated rubber bearings

Fukasawa, Tsuyoshi*; Miyagawa, Takayuki*; Uchita, Masato*; Yamamoto, Tomohiko; Miyazaki, Masashi; Okamura, Shigeki*; Fujita, Satoshi*

Nihon Kikai Gakkai Rombunshu (Internet), 87(898), p.21-00007_1 - 21-00007_17, 2021/06

This paper describes a fundamental study on the seismic safety margin for the isolated structure using laminated rubber bearings. The variation of the seismic response assumed in the isolated structure will occur under the superposition of "Variations in seismic response due to input ground motions" and "Error with design value accompanying manufacture of the isolation devices ". The seismic response analysis which allows to their conditions is important to assess the seismic safety margin for the isolated structure. This paper clarifies that the seismic safety margin of the isolated structure, which consists of rubber bearings, for Sodium-cooled Fast Reactor (SFR) is ensured against the basis ground motions of Japan Electric Association Guide 4601 (JEAG4601) and SFR through the seismic response analysis considering the variation factors of seismic response. In addition, a relationship between the seismic safety margin and the excess probability of linearity limits is discussed using the results of seismic response analysis.

Journal Articles

Uncertainty assessment of structural modeling in the seismic response analysis of nuclear facilities

Choi, B.; Nishida, Akemi; Muramatsu, Ken*; Takada, Tsuyoshi*

Transactions of the 24th International Conference on Structural Mechanics in Reactor Technology (SMiRT-24) (USB Flash Drive), 10 Pages, 2017/08

In order to clarify the influence of the modeling method on the result of seismic response analysis of nuclear facility, seismic response analysis using various simulated input ground motions was carried out and the uncertainty of response results were statistically analyzed. In particular, we focused on the difference of the response due to the structural modeling method (a conventional sway-rocking model and 3D FE model), and the relations among the input level, floor position, and response results were described and discussed.

Journal Articles

A Sensitivity analysis for construction of the seismic response analysis model of a nuclear reactor building by using a three-dimensional finite element model

Choi, B.; Nishida, Akemi; Nakajima, Norihiro

Kozo Kogaku Rombunshu, B, 63B, p.325 - 333, 2017/03

The Japan Atomic Energy Agency promotes research and development of three-dimensional vibration simulation technologies for nuclear facilities. In this paper, we report a seismic response analysis of the Tohoku Pacific Coast Earthquake using three-dimensional models of the High-Temperature Engineering Test Reactor (HTTR) building. We conducted a sensitivity study using input parameters with uncertainty. Furthermore, we examined the variation of the seismic response results against the input parameters.

Journal Articles

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake

Nakano, Takafumi; Sato, Fuminori; Shirozu, Hidetomo; Nakanishi, Ryuji; Fukuda, Kazuhito; Tachibana, Ikuya

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 57(1), p.14 - 20, 2015/01

no abstracts in English

Journal Articles

Design and evaluation methodology for seismic base isolation of nuclear components by probabilistic approach

Tsutsumi, Hideaki*; Ebisawa, Katsumi*; Yamada, Hiroyuki*; Shibata, Katsuyuki; Fujimoto, Shigeru*

Nihon Zairyo Gakkai JCOSSAR 2003 Rombunshu, p.829 - 836, 2003/11

no abstracts in English

JAEA Reports

Study on the dynamic response analysis for evaluating the effectiveness of base isolation for nuclear components

Mori, Kazunari*; Tsutsumi, Hideaki*; Yamada, Hiroyuki; Ebisawa, Katsumi; Shibata, Katsuyuki

JAERI-Tech 2001-037, 85 Pages, 2001/06

JAERI-Tech-2001-037.pdf:6.27MB

no abstracts in English

JAEA Reports

Shaking table test and dynamic response analysis of 3-D component base isolation system using multi-layer rubber bearings and coil springs

Tsutsumi, Hideaki*; Yamada, Hiroyuki; Ebisawa, Katsumi; Shibata, Katsuyuki; Fujimoto, Shigeru*

JAERI-Tech 2001-033, 124 Pages, 2001/06

JAERI-Tech-2001-033.pdf:9.98MB

no abstracts in English

JAEA Reports

Characteristics and dynamic response analysis of 3-D component base isolation system using ball bearings and air springs

Tsutsumi, Hideaki*; Yamada, Hiroyuki; Mori, Kazunari*; Ebisawa, Katsumi; Shibata, Katsuyuki

JAERI-Tech 2000-086, 93 Pages, 2001/02

JAERI-Tech-2000-086.pdf:6.56MB

no abstracts in English

Journal Articles

Dynamic behavior and base isolation effect of three dimensional base isolation test system for nuclear components

Tsutsumi, Hideaki*; Yamada, Hiroyuki; Ebisawa, Katsumi; Shibata, Katsuyuki; Fujimoto, Shigeru*

Doboku Gakkai Dai-2-Kai Menshin, Seishin Korokiumu Koen Rombunshu, p.75 - 82, 2000/11

no abstracts in English

JAEA Reports

Characteristics and dynamic resonse analysis of 3-D component base isolation system using multi-layer-rubber-bearings and coil springs

Tsutsumi, Hideaki*; Yamada, Hiroyuki; Ebisawa, Katsumi; Shibata, Katsuyuki

JAERI-Tech 2000-045, 107 Pages, 2000/07

JAERI-Tech-2000-045.pdf:7.25MB

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 3; Detailed checkup and comprehensive evaluation of installations in TRP

Fukuda, Kazuhito; Tomioka, Kenichiro*; Tachibana, Ikuya; Shirai, Nobutoshi; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 1; Background and outline

Nakano, Takafumi; Fukuda, Kazuhito; Sato, Fuminori; Kosaka, Ichiro; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 5; Detailed checkup and comprehensive evaluation of buildings in TRP

Sato, Fuminori; Nakanishi, Ryuji; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 2; Earthquake response analysis of installations in TRP

Koshino, Katsuhiko; Shirai, Nobutoshi; Sakaguchi, Shinobu; Shirozu, Hidetomo; Otaki, Miyuki*; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko; Tachibana, Ikuya

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 4; Earthquake response analysis of buildings in TRP

Nakanishi, Ryuji; Sato, Fuminori; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Study on reduction of vertical seismic response for JSFR

Yamamoto, Tomohiko; Kawasaki, Nobuchika; Ishikawa, Nobuyuki; Chikazawa, Yoshitaka; Fukasawa, Tsuyoshi*; Okamura, Shigeki*

no journal, , 

Due to the increase of the seismic condition for JSFR design study, the seismic condition for the design study of components is severer. This report explains the effect of study on reduction of vertical seismic response through the 3-dimensional FEM analysis focusing on study on reduction of vertical seismic response of main components that are critical in seismic feasibility. It also explains the integrity of vertical seismic response of FEM model and the mass model used in design studies with reflecting the vertical seismic response reduction.

28 (Records 1-20 displayed on this page)