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Journal Articles

Numerical study on effect of pressure on behavior of bubble coalescence by using CMFD simulation

Ono, Ayako; Suzuki, Takayuki*; Yoshida, Hiroyuki

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07

The mechanism of critical heat flux (CHF) for higher system pressure remains to be clarified, even though it is important to evaluate the CHF for the light water reactor (LWR) which is operated under the high pressure condition. In this study, the process of bubble coalescence was simulated by using a computational multi-fluid dynamics (CMFD) simulation code TPFIT under various system pressure in order to investigate the behavior of bubbles as a basic study. The growth of bubbles was simulated by blowing of vapor from a tiny orifice simulating bubble bottom. One or four orifices were located on the bottom surface in this simulation study. The numerical simulations were conducted by varying the pressure and temperature.

Journal Articles

Development of models for bubble turbulent diffusion and bubble diameter in multi-dimensional two-fluid model

Onuki, Akira; Akimoto, Hajime

Proceedings of 2nd Japanese-European Two-Phase Flow Group Meeting (CD-ROM), 6 Pages, 2000/00

no abstracts in English

Journal Articles

Study on growth evaluation for surface cracks, I; Fatigue behavior of flat plate specimen with surface cracks and Evaluation of crack growth behavior

; ; *; ;

Nihon Genshiryoku Gakkai-Shi, 27(3), p.250 - 261, 1985/00

 Times Cited Count:13 Percentile:81.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fatigue behavior of pipes containing multiple flaws in inner surface

; ; ; ;

Nucl.Eng.Des., 74(2), p.199 - 213, 1982/00

 Times Cited Count:1 Percentile:22.52(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fatigue Test Results of Straight Pipe with Flaws in Inner Surface

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JAERI-M 9246, 46 Pages, 1981/01

JAERI-M-9246.pdf:2.96MB

no abstracts in English

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