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Journal Articles

Critical power correlation for tight-lattice rod bundles

Liu, W.; Kureta, Masatoshi; Onuki, Akira; Akimoto, Hajime

Journal of Nuclear Science and Technology, 42(1), p.40 - 49, 2005/01

 Times Cited Count:7 Percentile:44.75(Nuclear Science & Technology)

In this research, critical power correlation for tight-lattice rod bundles is newly proposed using 7-rod axially uniform-heated data, 7-rod and 37-rod axially double-humped-heated data at Japan Atomic Energy Research Institute (JAERI). For low mass velocity region ($$<$$ 300 kg/m$$^{2}$$s), the correlation is written in critical quality - annular flow length type. For high mass velocity region ($$>$$ 300 kg/m$$^{2}$$s), it is written in local critical heat flux - critical quality type. The standard deviation of ECPR (Experimental Critical Power Ratio) to the whole JAERI data (694 data points) is 6%. The correlation is verified by Bettis Atomic Power Laboratory data (177 points, standard deviation: 7.7%). The correlation is confirmed being able to give good prediction for the effects of mass velocity, inlet temperature, pressure and heated equivalent diameter on critical power. The applicable range of the correlation is: gap between rods from 1.0 to 2.29 mm, heated length from 1.26 to 1.8 m, mass velocity from 150 to 2000 kg/m$$^{2}$$s and pressure from 2 to 11 MPa.

Journal Articles

High heat load test of CFC divertor target plate with screw tube for JT-60 superconducting modification

Masaki, Kei; Taniguchi, Masaki; Miyo, Yasuhiko; Sakurai, Shinji; Sato, Kazuyoshi; Ezato, Koichiro; Tamai, Hiroshi; Sakasai, Akira; Matsukawa, Makoto; Ishida, Shinichi; et al.

Fusion Engineering and Design, 61-62, p.171 - 176, 2002/11

 Times Cited Count:19 Percentile:74.62(Nuclear Science & Technology)

A flat carbon fiber composite tile mock-up with screw tubes, which have helical fins like a nut, was fabricated aiming at further improvement of the heat removal performance of the cost-effectively manufactured divertor target for JT-60SC (modified JT-60 as a superconducting coil tokamak). The heat removal performance of the mock-up was successfully demonstrated on the JAERI Electron Beam Irradiation Stand. The estimated heat transfer coefficient of the screw tube at the non-boiling region was roughly 3 times higher than that of the smooth tube. This corresponds to 1.5 times that of the swirl tube. A heat cycle test of 10 MW/m2 showed that the mock-up with the screw tubes could withstand for 1400 cycles. These results indicate that the divertor target plate with the flat carbon fiber composite tile and the screw tube can be a promising candidate for the JT-60SC divertor target.

Journal Articles

Experiments on heat transfer of smooth and swirl tubes under one-sided heating conditions

Araki, Masanori; Ogawa, Masuro; Kunugi, Tomoaki; Sato, Kazuyoshi;

Int. J. Heat Mass Transfer, 39(14), p.3045 - 3055, 1996/00

 Times Cited Count:72 Percentile:94.13(Thermodynamics)

no abstracts in English

JAEA Reports

Journal Articles

A Powerful solution algorithm for single-stage flash problems

;

Comput.Chem.Eng., 10(4), p.353 - 363, 1986/00

 Times Cited Count:6 Percentile:57.56(Computer Science, Interdisciplinary Applications)

no abstracts in English

Oral presentation

Evaluation method using material analysis of specimen in plasma heating experiment, 1; Outline of evaluation method using material analysis of specimen in plasma heating experiment

Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Yamaguchi, Hidenobu*; Maruyama, Shinichiro*

no journal, , 

no abstracts in English

Oral presentation

Establishment of evaluation method using material analysis of simulated fuel assembly heating test, 1; Outline of simulated fuel assembly heating test using non-transfer type plasma heating

Abe, Yuta; Nakagiri, Toshio; Yamashita, Takuya; Noro, Junji*; Matsushima, Tomohiro*; Kawakami, Tomohiko*

no journal, , 

no abstracts in English

Oral presentation

Development of plasma heating technology for simulation of LWR severe accident behavior, 2; Outcomes of JFY2015

Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Nagae, Yuji; Ishimi, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Development of plasma heating technology for simulation of LWR severe accident behavior, 1; Objectives and JFY2014 outcomes

Sato, Ikken; Abe, Yuta; Nakagiri, Toshio; Nagae, Yuji; Ishimi, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Development of plasma heating technology for simulation of LWR severe accident behavior, 3; Consideration of a wide range of oxygen mapping analysis method using the EPMA

Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Tanaka, Hiroshi*; Yamaguchi, Hidenobu*

no journal, , 

no abstracts in English

Oral presentation

Consideration of material analysis using simulated fuel assembly heating test, 1; Outline of evaluation in simulated fuel assembly heating test

Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Yamaguchi, Hidenobu*

no journal, , 

no abstracts in English

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