Search Results - "Ishitsuka, E"

Irradiation test of component for radiation-resistant small sized motor by Nakamichi, M., Ishitsuka, E., Shimakawa, S., Kan, S.

“…A small-sized motor with a resistance to radiation was developed. This motor has been able to operate at a gamma-ray dose of a value 700 times as high as the…”
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Tritium release properties of neutron-irradiated Be12Ti by Uchida, M., Ishitsuka, E., Kawamura, H.

“…Be12Ti has a high melting point and good chemical stability and is a promising advanced material for the neutron multiplier of the DEMO reactor that requires…”
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Application of Pade approximation for calculation of epithermal neutron self-shielding factors of some materials dealing with Doppler broadening effects by Phuong, H.T., Nhon, M.V., Trang, V.T.T., Ishitsuka, E.

“…The Pade approximation method has been applied to calculate the epithermal neutron self-shielding factors for some materials used as a comparator in k…”
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Irradiation tests of a small-sized motor with radiation resistance by Nakamichi, M., Ishitsuka, E., Shimakawa, S., Kan, S.

“…A small-sized motor with a resistance to neutron and gamma-ray radiation was developed. This motor was rotating normally at a gamma-ray dose of 7 × 10 8 Gy, a…”
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Thermal conductivity of neutron irradiated Be12Ti by UCHIDA, M, ISHITSUKA, E, KAWAMURA, H

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In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation by Tsuchiya, K, Kikukawa, A, Hoshino, T, Nakamichi, M, Yamada, H, Yamaki, D, Enoeda, M, Ishitsuka, E, Kawamura, H, Ito, H, Hayashi, K

“…A binary pebble bed of lithium titanate (Li2TiO3) was irradiated in the Japan Materials Testing Reactor (JMTR), and its tritium recovery characteristics bed…”
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High heat flux performance of neutron irradiated plasma facing components by Rödig, M, Ishitsuka, E, Gervash, A, Kawamura, H, Linke, J, Litunovski, N, Merola, M

“…During the operation of ITER, the plasma facing components will undergo different kinds of thermal loadings like thermal fatigue, vertical displacement events…”
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Radiation-induced thermoelectric sensitivity in the mineral-insulated cable of magnetic diagnostic coils for ITER by Nishitani, T, Vayakis, G, Yamauchi, M, Sugie, T, Kondoh, T, Shikama, T, Ishitsuka, E, Kawashima, H

“…Magnetic coils are indispensable for plasma position control in tokamaks. For ITER, non-inductive voltages generated under irradiation have to be reduced to…”
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Application of beryllium intermetallic compounds to neutron multiplier of fusion blanket by Kawamura, H, Takahashi, H, Yoshida, N, Shestakov, V, Ito, Y, Uchida, M, Yamada, H, Nakamichi, M, Ishitsuka, E

“…Beryllium metal is commonest as a neutron multiplier of fusion blanket. However, the application of beryllium metal to DEMO reactor that requires higher…”
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Feasibility study of Tritium recoil barrier forneutron reflectors by Ishitsuka, E., Sakamoto, N.

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Feasibility study of Tritium recoil barrier forneutron reflectors by E. Ishitsuka, N. Sakamoto

“…Tritium release into the primary coolant of the research and test reactors during operation had been studied, and it is found that the beryllium components…”
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In-situ irradiation test of mica substrate bolometer at the JMTR reactor for the ITER diagnostics by Nishitani, T, Shikama, T, Reichle, R, Hodgson, E.R, Ishitsuka, E, Kasai, S, Yamamoto, S

“…Irradiation tests of a mica substrate bolometer were carried out at the Japan Materials Testing Reactor up to the fast neutron fluence of 0.1 dpa. A…”
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Effects of helium production and radiation damage on tritium release behavior of neutron-irradiated beryllium pebbles by Ishitsuka, E, Kawamura, H, Terai, T, Tanaka, S

“…The tritium release from neutron-irradiated beryllium pebbles, irradiated under different helium production (0.5–1.0 × 10 3 appm He) and dpa (4.2–8.6)…”
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Heat load test of Be/Cu joint for ITER first wall mock-ups by Uchida, M., Ishitsuka, E., Hatano, T., Barabash, V., Kawamura, H.

“…Bonding by hot isostatic pressing with an interlayer has been developed as a joining technology of beryllium (Be)/alumina dispersion strengthened copper, a…”
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Microstructure and mechanical properties of neutron irradiated beryllium by Ishitsuka, E., Kawamura, H., Terai, T., Tanaka, S.

“…Microstructure and mechanical properties of the neutron irradiated beryllium were studied. Specimens were produced by various methods and had different grain…”
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Development of EC H&CD launcher components for fusion device by Takahashi, K., Ishitsuka, E., Moeller, C.P., Hayashida, K., Kasugai, A., Sakamoto, K., Hayashi, K., Imai, T.

“…The critical issues of an EC H&CD launcher are studied for a fusion device like International Thermonuclear Experimental Reactor (ITER). The key components of…”
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Calculation of tritium release from driver fuels into primary coolant of research reactors by Hai Quan Ho, E. Ishitsuka

“…Increasing of tritium concentration in the primary coolant of the research and test reactors during operation had been reported. To check the source for…”
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MCNP6 calculation of neutron flux map in the httr during normal operation by Ho, H.Q., Ishitsuka, E., Iigaki, K.

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In situ characterization of a small sized motor under neutron irradiation by Ishitsuka, E, Kan, S, Kawamura, H, Onozawa, H

“…In order to conduct the integrated irradiation experiment of fusion blanket with testing reactor, it is indispensable to develop a small motor with high…”
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Evaluation of tritium release curve in primary coolant of research reactors by E. Ishitsuka, I. E. Kenzhina

“…Increase of tritium concentration in the primary coolant for the research and testing reactors during reactor operation had been reported. To clarify the…”
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