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Ono, Ayako; Tanaka, Masaaki; Kobayashi, Jun; Kamide, Hideki
Mechanical Engineering Journal (Internet), 4(1), p.16-00217_1 - 16-00217_15, 2017/02
In the design of the Advanced Sodium-cooled Fast Reactor in Japan, the Reynolds number in the primary hot leg (H/L) piping reaches 4.2
10
. Furthermore, a short elbow is used in the H/L piping to achieve a compact plant layout. In the H/L piping, flow-induced vibration is a concern due to the excitation force caused by pressure fluctuation in the short elbow. In this report, the influence of inlet velocity condition on the unsteady velocity characteristics in the short elbow was studied by controlling the flow patterns at the elbow inlet. Measured velocity distributions indicated that the inlet velocity profiles affected a circumferential secondary flow, which then affected an area of flow separation at the elbow. It was also found that the velocity fluctuation at low frequency components observed upstream of the elbow could remain in downstream of the elbow though its intensity was attenuated.
Yanagisawa, Kazuaki; Takahashi, Shoji; Narita, Osamu; Yonezawa, Minoru
IAEA-CN-123/03/P/18 (CD-ROM), 9 Pages, 2004/10
To understand a socio-economic effect of basic research in JAERI, the stimulation and promotion of social interrelations through a formation of networking was studied quantitatively. (1)Worldwide trend of MS was studied by INIS by means of top {100} keywords as input. Research activity of MS in JAERI represented by top {100} keywords is not much different from that of other nuclear advanced countries participated to INIS. (2)Emphasized basic research fields (EBRF) of MS in JAERI can be clarified by selected keywords of "ion irradiation" and "actinides", those have a strong relation to nuclear. For actinides, the growth rate of networking between JAERI and PS was of order of 3-4% per 25 years and 8% per recent 5 years. The rate of networking formation is markedly increased recently. (3)Between JAERI and the other 5 selected research bodies, only 7 out of over 110 keywords such as "neutron" and "accelerators" were overlapped. In the overlapped region the two compensated and uplifted the national standard level each other.
Matsuura, Shojiro; ; ; ; Umezawa, Hirokazu;
Journal of Nuclear Science and Technology, 12(1), p.24 - 34, 1975/01
Times Cited Count：23no abstracts in English
Yamane, Yuichi; Abe, Hitoshi
no journal, ,
After the experience of the accident at the Fukushima Dai-ichi Nuclear Power Plants of Tokyo Electric Power Company (TEPCO),Japan's nuclear safety standard for reprocessing plant has been renewed and the standard now requires accident management measures and the assessment of their effectiveness to the severe accident such as criticality accident. This paper summarizes the issues for the best estimation in criticality accident consequence analysis and proposes a new method to estimate source term in criticality accident. Unique characters of criticality accident in nuclear fuel facilities, such as the production of short life nuclides, are described in association with the best estimation of public and worker's dose. In the light of those characters, this paper proposes a procedure to estimate source term in criticality accident by utilizing five-component equation described in DOE handbook.
