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JAEA Reports

Dynamic analysis of ITER tokamak based on results of vibration test using scaled model

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka

JAERI-Tech 2004-072, 43 Pages, 2005/01

JAERI-Tech-2004-072.pdf:6.06MB

The vibration experiments of the support structures with flexible plates for the ITER major components such as the vacuum vessel (VV) and the toroidal field (TF) coil were performed aiming to obtain its basic mechanical characteristics. Based on the experimental results, numerical analysis regarding the actual support structure was performed and a simplified model of the support structure was proposed. A support structure was modeled by only two spring elements. The stiffness calculated by the spring model agrees well with that of shell model, simulating actual structures based on the experimental results. It is therefore found that the spring model with the only two values of stiffness enables to simplify the complicated support structure with flexible plates. Using the spring model, the dynamic analysis of the VV and TF coil were performed to estimate the integrity under the design earthquake. As a result, the maximum relative displacement of 8.6 mm between VV and TF coil is much less than designed clearance, 100 mm, so that the integrity of the components is ensured.

Journal Articles

Dynamic analysis of ITER tokamak using simplified model for support structure

Takeda, Nobukazu; Shibanuma, Kiyoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.988 - 990, 2004/11

The simplified analytical model of the support structure composed of complicated structures such as multiple flexible plates was proposed for the dynamic analysis of the ITER major components of VV and TF coil. The support structure composed of flexible plates and connection bolts was modeled as a spring model composed of only two spring elements including the effect of connection bolts. The stiffness of both spring models for VV and TF coil agree well with that of shell models simulating actual structures such as flexible plates and connection bolts. Using the proposed model, the dynamic analysis of the VV and TF coil for the ITER were performed to estimate the integrity under the design earthquake at Rokkasho, a candidate of ITER site. As a result, it is found that the maximum relative displacement of 8.6 mm between VV and TF coil is much less than 100 mm, so that the integrity of the major components are ensured for the expected earthquake event.

Journal Articles

Development of simplified computer codes for impact analysis of radioactive materials transport casks, 1st report; Computer code CRUSH for impact analysis of casks with shock absorbers

; *

Nihon Genshiryoku Gakkai-Shi, 33(4), p.381 - 390, 1991/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Dynamic Behavior of Pipe under Loss of Coolant Accident

Ueda, Shuzo

JAERI-M 87-027, 179 Pages, 1987/03

JAERI-M-87-027.pdf:5.43MB

no abstracts in English

Journal Articles

JAEA Reports

Stress Intensity Factor Analyses of Surface Cracks in Three-Dimensional Structures

*; ; *; *

JAERI-M 83-189, 44 Pages, 1983/11

JAERI-M-83-189.pdf:1.05MB

no abstracts in English

JAEA Reports

Journal Articles

Simplified analytical model for HTGR core seismic response

; *

Journal of Nuclear Science and Technology, 16(8), p.605 - 612, 1979/00

 Times Cited Count:2

no abstracts in English

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