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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.
Someya, Takayuki*; Chitose, Hiromasa*; Watanabe, Satoshi*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 9 Pages, 2019/05
In this study, CFD analysis has been conducted for the assessment of spent fuel integrity in large LOCA event and the maximum temperature of spent fuel assemblies has been evaluated. Then, it has been compared with the result of the simple assessment method. As a case study, additional CFD analysis has been conducted, where water level in SFP decreases to the Bottom of Active Fuel (BAF) due to boil-off. Since this scenario might be more severe than large LOCA scenario, the number of spent fuel assemblies, their decay heat and loading pattern to maintain spent fuel integrity are investigated.
; ; Yamazaki, Toshihiko; ; ; Kondo, Toshinari*; *
JNC TN8400 2001-030, 99 Pages, 2002/01
JNC-TN8400-2001-030.pdf:13.24MB
There is a great deal of that we build a Base-Isolated building with the quaternary deposit ground. In an atomic energy institution, a study request is strong. When we build a Base-Isolated building with the quaternary deposit ground, evaluation of earthquake vibration of a vertical direction is an important problem. In an atomic energy institution, we design it by big earthquake load, and therefore examination is necessary. And, in this study, we do examination to build a Base-Isolated building with the quaternary deposit ground, we report it about an evaluation method of a design. Furthermore, we report that we estimated pipe laying and machinery to put in a building of Base-lsolated.
Nakahara, Yoshinori; Suyama, Kenya; Suzaki, Takenori
JAERI-Tech 2000-071, 381 Pages, 2000/10
JAERI-Tech-2000-071.pdf:17.6MB
no abstracts in English
*; *
JNC TJ9400 2000-004, 109 Pages, 2000/02
JNC-TJ9400-2000-004.pdf:4.96MB
We estimated covariances of the JENDL-3.2 data on the nuclides and reactions needed to analyze fast-reactor cores for the past three years, and produced covariance files. The present work was undertaken to re-examine the covariance files and to make some improvements. The covariances improved are the ones for the inelastic scattering cross section of 
O, the total cross section of 
Na, the fission cross section of 
U, the capture cross section of 
U, and the resolved resonance parameters for U. Moreover, the covariances of 
U data were newly estimated by the present work. The covariances obtained were compiled in the ENDF-6 format.
Shinohara, Yoshinori*; Tsujimoto, Keiichi*
JNC TJ1400 2000-002, 280 Pages, 2000/02
JNC-TJ1400-2000-002.pdf:9.57MB
no abstracts in English
Shinohara, Yoshinori*; Tsujimoto, Keiichi*
JNC TJ1400 2000-001, 137 Pages, 2000/02
JNC-TJ1400-2000-001.pdf:4.19MB
no abstracts in English
JNC TN9400 99-041, 187 Pages, 1999/05
lt is widely recognized that the current seismic design methods for piping involve a large amount of safety margin. From this viewpoint, a series of seismic analyses and evaluations with various design codes were made on typical LMFBR main sodium piping systems. Actual capability against seismic loads were also estimated on the piping systems. Margins contained in the current codes were quantified based on these results, and potential benefits and impacts to the piping seismic design were assessed on possible mitigation of the current code allowables. From the study, the following points were clarified; (1)A combination of inelastic time history analysis and true(without margin) strength capability allows several to twenty times as large seismic load compared with the allowable load with the current methods. (2)The new rule of the ASME is relatively compatible with the results of inelastic analysis evaluation. Hence, this new rule might be a goal for the mitigation of seismic design rule. (3)With this mitigation, seismic design accommodation such as equipping with a large number of seismic supports may become unnecessary.
Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka
Transactions of the American Nuclear Society, 75, 207 Pages, 1996/00
no abstracts in English
Yamamoto, Toshihiro; *
JAERI-M 93-218, 18 Pages, 1993/11
no abstracts in English
Asahi, Yoshiro; ;
Journal of Nuclear Science and Technology, 24(5), p.365 - 376, 1987/05
Times Cited Count：1 Percentile：19.33(Nuclear Science & Technology)no abstracts in English
