著者
YASKAWA Hirosi
出版者
一般社団法人日本機械学会
雑誌
機械學會誌
巻号頁・発行日
vol.31, no.129, pp.1-12, 1928-01-20

The allowance for force-fit is in practice given by the diameter alone, independently on the materials, the outer diameter of the boss and the inner diameter of the shaft. The author starting from the stress equations of thick cylinder of infinite length, constructed a new chart for the determination of the theoretical value of allowance taking these factors into consideration. And the application of the chart to the calculation of the maximum stresses induced by force-fit is also introduced with an example.
著者
幡中 憲治 藤満 達朗 安藤 隆之 橘 輝夫 中居 嘉一郎
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. A編 (ISSN:03875008)
巻号頁・発行日
vol.55, no.512, pp.773-781, 1989-04-25
被引用文献数
1

The test system was newly developed for evaluating precisely the strength of ceramics at elevated temperatures, being equipped with the laser beam-type displacement measuring system. Four-point bending tests were performed on the silicon-nitride ceramics at elevated temperatures from 800℃ to 1300℃. The linear relationship held between the load, P and the displacement, 6 at test temperatures below 1200℃. The P vs. δ plot, however, deviated from the linear relationship at temperatures above 1200℃, suggesting the occurrence of plastic deformation. The flexural strength remained unchanged in the test temperature range from room temperature to about 900℃, and then this decreased gradually with further increase in the test temperature. The fracture toughness measured by using the Chevron notch-type specimen was nearly constant in the temperature range from room temperature to about 1100℃. The fracture toughness obtained from the Knoop-indented specimen was discussed in comparison with that from the Chevron notch-type specimen.
著者
田中 創 山崎 博司 寺地 誠喜 瀬川 大資 角田 敏一
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. B編 (ISSN:03875016)
巻号頁・発行日
vol.71, no.702, pp.690-695, 2005-02-25
参考文献数
10
被引用文献数
3

An experimental study has been carried out to reveal the statistical characteristics for the onset of micro-explosion of an emulsion droplet burning on a hot surface. Detail measurements of the waiting time for the onset of micro-explosion are made for various properties of base fuel, water contents and surface temperatures. The Weibull analysis is applied to obtain the distribution function of the waiting time for the onset of micro-explosion and to derive the empirical formula for the rate of micro-explosion as a function of water volume and emulsion temperature. The base fuels employed are n-decane, n-dodecane, n-tetradecane and n-hexadecane. The results show that the waiting time is correlated well with the Weibull distribution of the wear-out type. The mean waiting time decreases with an increase in the boiling point of base fuel, water content and surface temperature. An empirical formula is proposed for the rate of micro-explosion as a function of water volume and emulsion temperature.
著者
永瀬 和彦 近藤 和宏 野村 俊明
出版者
一般社団法人日本機械学会
雑誌
日本機械学会論文集. C編 (ISSN:03875024)
巻号頁・発行日
vol.63, no.606, pp.620-627, 1997-02-25
参考文献数
6
被引用文献数
3

Many trains were derailed and damaged by the earthquake in Kobe on January 17, 1995. At the same time, many railway girder bridges and viaducts were seriously damaged by the quake. It was postulated that serious accidents could occur as a result of trains running at high speeds into these girder bridges or viaducts. Fortunately, no fatal accidents occurred. On investigating such accidents, the authors found that they rarely occur, because a train derailed by the violent shock of a quake is so radically decelerated by the huge running resistance caused by the derailment that it stops just after the quake. On the other hand, it takes some time until the bridges or viaducts collapse after the quake.
著者
関山 浩介 福田 敏男 松村 司郎 山田 康二
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. C編 (ISSN:03875024)
巻号頁・発行日
vol.63, no.605, pp.196-203, 1997-01-25
参考文献数
12
被引用文献数
2

This paper deals with a modeling and controlling strategy for multirobot group behavior. While the distributed autonomous robot system has the advantage of flexibility, it also has difficulties in coordinating global system such that the designer expects. We present a methodology for the designing issue for group robotics. Self-organization is a natural principle in a dissipative system. Utilizing this principle, we present the top-down and bottom-up hybrid approach and a basic model for coordinating macro-scale group behavior as a framework for the self-organizing control of group behavior. Then we present the model of strategy formation in the system based on the opinion formation model. The analytical predicted group behavior is verified by simulation results. In particular, we realize self-organization of temporal behavior pattern in group-level cooperation.
著者
結城 良治 北川 英夫 東郷 敬一郎
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. A編 (ISSN:03875008)
巻号頁・発行日
vol.47, no.422, pp.981-989, 1981-10-25
被引用文献数
2

本報は, 従来のデータの得られていなかった二軸荷重重下の疲労き裂成長の低ΔK_I 領域特性と下限界条件ΔK_<Ith> を高張力鋼きつき系統的に調べ, またこの疲労き裂の開閉挙動を調べたものである. その結果, 二軸荷重下のき裂成長特性は, 単軸荷重下の場合と同様にΔK_Iと応力比 R_K(=K_<I min>/K_<I max>) あるいはΔK_<Ieff> で統一的に特性づけられることを明らかにした. 本実験では, き裂に平行な応力(非特異定数項)の影響は認められなかった.
著者
大森 修一 奈良林 直 森 治嗣 渡邉 史紀
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. B編 (ISSN:03875016)
巻号頁・発行日
vol.75, no.751, pp.403-405, 2009-03-25

A Steam Injector (SI) is a simple, compact and passive pump. We are developing this innovative concept by applying the SI system for core injection system in emergency core cooling systems (ECCS) to further improve the safety of nuclear power plants. Passive ECCS in nuclear power plants would be inherently very safe and would prevent severe accidents by keeping the core covered with water (Severe accident-free concept). The passive core injection system (PCIS) driven by high-efficiency SI is a system that, in an accident such as a LOCA, attains a higher discharge pressure than the supply steam pressure used to inject water into the reactor by operating the SI. This report describes the experiments and the analytical simulation on a SI-driven PCIS for innovative-simplified nuclear power plant. In addition, we conducted the analytical simulations of SI, which grew in size for the actual nuclear power plant.
著者
木村 暢之 小林 順 上出 英樹
出版者
一般社団法人日本機械学会
雑誌
年次大会講演論文集 : JSME annual meeting
巻号頁・発行日
vol.2009, no.3, pp.163-164, 2009-09-12

Hot and cold fluids are mixed at the core outlet of sodium cooled fast reactors. The temperature fluctuation causes high cycle thermal fatigue in structural components. The temperature fluctuation at the core outlet region has not a sinusoidal waveform but an irregular spike waveform. In the study, the evaluation method for the high cycle thermal fatigue was investigated against the spike waveform of temperature fluctuation. It was found that the combinational method between the peak-to-peak value of temperature fluctuation and the frequency response function of structure could evaluate the fatigue damage in structure.
著者
山本 泰 武内 豊 白川 健悦 師岡 慎一
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. B編 (ISSN:03875016)
巻号頁・発行日
vol.75, no.751, pp.397-399, 2009-03-25

In the envisioned high-power density core plant, the degradation of stability is concerned that is attributed to the shortening of rod heat conduction time constant upon the dense fuel grid and the increment of pressure drop caused by the wall friction. Under power and flow oscillating conditions, the two-phase flow behavior might be different from that under the steady conditions. Therefore, the thermal-hydraulic test using the rod bundle under oscillating conditions were performed to obtain the verification data for the analysis code. In this paper, the test results were described. It was found that the critical power decreased under flow oscillating conditions compared with under steady conditions, and the power oscillation had a little effect on the critical power.
著者
野崎 謙一朗 大川 富雄 堀田 亮年
出版者
一般社団法人日本機械学会
雑誌
日本機械学會論文集. B編 (ISSN:03875016)
巻号頁・発行日
vol.75, no.751, pp.400-402, 2009-03-25

In the envisioned high-power density core plant, the degradation of stability is concerned that is attributed to the shortening of rod heat conduction time constant upon the dense fuel grid and the increment of pressure drop caused by the wall friction. To confirm the influence of such degradation on the fuel soundness, the bundle geometry critical power test was held under flow-power oscillation condition which envisages the unstable phenomenon occurring under in the flow transient event. This paper describes the analysis results of the cited test with sub-channel code NASCA, and the discussion of the mechanism of boiling transition under flow-power oscillating condition.