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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

Journal Articles

A Nuclear reactor installed in the basement of a building for heat supply

Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Fukuhara, Yoshifumi*; Nakajima, Nobuya; Ochiai, Masaaki

Proceedings of the 4th JSME-KSME Thermal Engineering Conference, p.1_61 - 1_66, 2000/00

no abstracts in English

JAEA Reports

Re-evaluation of Seismic design for JOYO buildings and equipments

Isozaki, Kazunori;

PNC TN9410 97-069, 134 Pages, 1997/07

PNC-TN9410-97-069.pdf:3.78MB

Hyougo-ken southern earthquake broke out in 1997/01/17. The Atomic Energy Safety Co㎜ission considered reasonable of the design guide for seismic design. And the Science and Technology Agency(STA) required reevaluation of atomic power facilities built by old design guide according to the new seismic design guide. JOYO obtained the construction license in 1970/02. Heat transport system and buildings of JOYO was reevaluated by the new seismic design guide for the MK-III project. So, JOYO was not required reevaluation by STA. But, this evaluation of MK-III was limited to reconstruction area, and the seismic design was reevaluated extensively to confirm earthquake proof characteristics. The structural integrity of buildings and equipments was confirmed by the result of reevaluation by the new seismic design guide. The analysis model conditions were established according to the 1987 and 1991 version of JEAG. This was done by ground investigation result and buildings vaibration test. It was made clear that the analysis model conditions were reasonable and conservative from a technical view point.

JAEA Reports

JAEA Reports

None

; *; ; ; ; ;

PNC TN8470 93-002, 99 Pages, 1993/01

PNC-TN8470-93-002.pdf:2.05MB

no abstracts in English

JAEA Reports

Bowing reactivity analysis of FFTF core

Yamaoka, Mitsuaki; Hayashi, Hideyuki

PNC TN9410 92-368, 75 Pages, 1992/12

PNC-TN9410-92-368.pdf:1.49MB

A passive safety test phase IIB is planned at the FFTF (Fast Flux Test Facility) core to assess the reactivity feedback effect related to passive safety feature of FBRs, especially the effect due to core deformation. For pre-test analyses of the test, a bowing reactivity analysis has been carried out for FFTF core. The bowing reactivity is analyzed based on core displacement data evaluated postulating ULOF (Unprotected Loss of Flow) event at 30% rated flow. In the analysis, fuel reactivity worth distribution is expressed as function on the reference core without deformation and the bowing reactivity is calculated based on the first-order perturbation theory. This report summarizes the relationships between power to flow ratio and the bowing reactivity with clearance between subassembly load pads and that between the core and the core restraint system as parameters. Followings are main results. (1)As the power to flow ratio increases, a positive reactivity is added to the core by the core deformation until clearance between subassembly load pads doses. This is due to the inward displacement of active core caused by mechanical interactions of subassemblies. (2)After the closure of clearance between subassembly load pads, the active core begins to move outwards, and a negative reactivity is added to the core. (3)The deformation behavior of the outermost subassemblies of the core dominates the bowing reactivity since both the magnitude of deformation and the reactivity effect for unit displacement are large compared with those of others. For the analysis, a code for bowing reactivity calculation has been developed. The calculation method and the manual are also presented in this report.

Journal Articles

Bending strength and fatigue behavior of nuclear-grade graphite under impact load

Futakawa, Masatoshi; Kikuchi, Kenji; ; *

Zairyo, 40(449), p.178 - 184, 1991/02

no abstracts in English

JAEA Reports

Throughput Calibration Methods for Piezoelection Valves of JT-60

; ; ; *

JAERI-M 84-097, 31 Pages, 1984/05

JAERI-M-84-097.pdf:0.71MB

no abstracts in English

44 (Records 1-20 displayed on this page)