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Journal Articles

Optimum temperature for HIP bonding invar alloy and stainless steel

Wakui, Takashi; Ishii, Hideaki*; Naoe, Takashi; Kogawa, Hiroyuki; Haga, Katsuhiro; Wakai, Eiichi; Takada, Hiroshi; Futakawa, Masatoshi

Materials Transactions, 60(6), p.1026 - 1033, 2019/06

 Times Cited Count:1 Percentile:13.55(Materials Science, Multidisciplinary)

The mercury target has large size as 1.3$$times$$1.3$$times$$2.5 m$$^{3}$$. In view of reducing the amount of wastes, we studied the structure so that the fore part could be separated. The flange is required to have high seal performance less than 1$$times$$10$$^{-6}$$ Pa m$$^{3}$$/s. Invar with low thermal expansion is a candidate. Due to its low stiffness, however, the flange may deform when it is fastened by bolts. Practically invar is reinforced with stainless steel where all interface between them has to be bonded completely with the HIP bonding. In this study, we made specimens at four temperatures and conducted tensile tests. The specimen bonded at 973 K had little diffusion layer, and so fractured at the interface. The tensile strength reduced with increasing the temperature, and the reduced amount was about 10% at 1473 K. The analyzed residual stresses near the interface increased by 50% at maximum. Then, we concluded that the optimum temperature was 1173 K.

Journal Articles

Performance of new gas-filled recoil ion separator GARIS-II for asymmetric fusion reaction

Kaji, Daiya*; Morimoto, Koji*; Wakabayashi, Yasuo*; Takeyama, Mirei*; Yamaki, Sayaka*; Tanaka, Kengo*; Haba, Hiromitsu*; Huang, M.*; Murakami, Masashi*; Kanaya, Jumpei*; et al.

JPS Conference Proceedings (Internet), 6, p.030107_1 - 030107_4, 2015/06

Performance of the new gas-filled recoil ion separator GARIS-II was investigated using asymmetric $$^{22}$$Ne-induced fusion reactions. The use of He-H$$_{2}$$ mixture gas for the gas-filled magnet significantly reduced background scattered particles detected at the focal-plane Si detector, and increased a transmission of the asymmetric reaction products. A target-identification system was newly installed for efficient measurements of excitation functions without changing beam energy nor target.

Journal Articles

Annealing of electron irradiated, thick, ultrapure 4H SiC between 1100$$^{circ}$$C and 1500$$^{circ}$$C and measurements of lifetime and photoluminescence

Klahold, W. M.*; Devaty, R. P.*; Choyke, W. J.*; Kawahara, Kotaro*; Kimoto, Tsunenobu*; Oshima, Takeshi

Materials Science Forum, 778-780, p.273 - 276, 2014/02

Journal Articles

1 MeV, ampere class accelerator R&D for ITER

Inoue, Takashi; Kashiwagi, Mieko; Taniguchi, Masaki; Dairaku, Masayuki; Hanada, Masaya; Watanabe, Kazuhiro; Sakamoto, Keishi

Nuclear Fusion, 46(6), p.S379 - S385, 2006/06

 Times Cited Count:33 Percentile:75.73(Physics, Fluids & Plasmas)

The JAERI MeV accelerator has been designed extrapolating vacuum insulation design guidelines (the clump theory and Paschen law) to Mega Volt and long vacuum gap. Reduction of electric field concentration at triple junction by a large stress ring was effective to prevent flashover along insulator surface. By the vacuum insulation technology above, the accelerator sustained 1 MV for 8,500 s continuously. Strong enhancement of negative ion surface production has been attained by stopping vacuum leaks due to SF$$_{6}$$ permeation through Viton O rings and a damage of port by backstream ions, followed by increase of the H$$^{-}$$ ion current density without saturation. Operating the KAMABOKO source with high power arc discharge ($$leq$$ 40 kW), H$$^{-}$$ ion beams of 146 A/m$$^{2}$$ (total ion current: 0.2 A) have been obtained stably at the beam energy of 836 keV (pulse length: $$geq$$ 0.2 s). Bremsstrahlung generation in the accelerator is also estimated from EGS4 analysis, and then discussion on the breakdown possibility follows.

Journal Articles

Evaluation of tritium behavior in the epoxy painted concrete wall of ITER hot cell

Nakamura, Hirofumi; Hayashi, Takumi; Kobayashi, Kazuhiro; Nishi, Masataka

Fusion Science and Technology, 48(1), p.452 - 455, 2005/07

 Times Cited Count:2 Percentile:18.81(Nuclear Science & Technology)

Tritium behavior released in ITER hot cell has been investigated numerically. Tritium behavior was evaluated by a combined analytical methods of a tritium transport analysis with the one dimensional diffusion model in the multi-layer wall (concrete and epoxy paint) and a tritium concentration analysis with the complete mixing model by the ventilation in the hot cell under the simulated hot cell operational conditions. As the results, tritium concentration in the hot cell volume decreases rapidly from 300 DAC (Derived Air Concentration) less than 1 DAC in several days after removing the tritium release source. Tritium inventory in the wall is estimated to be about 0.1 PBq for 20 years operation. On the other hand, Tritium permeation through the epoxy painted concrete wall will be negligible. Finally, as to the effect of epoxy paint on the tritium permeation and inventory, it is found that the epoxy paint can reduce tritium inventory by about two orders of magnitude relative to bare concrete wall.

Journal Articles

Present status of the liquid lithium target facility in the international fusion materials irradiation facility (IFMIF)

Nakamura, Hiroo; Riccardi, B.*; Loginov, N.*; Ara, Kuniaki*; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; et al.

Journal of Nuclear Materials, 329-333(1), p.202 - 207, 2004/08

 Times Cited Count:14 Percentile:68.23(Materials Science, Multidisciplinary)

International Fusion Materials Irradiation Facility (IFMIF), being developed by EU, JA, RF and US, is a deuteron-lithium (Li) reaction neutron source for fusion materials testing. In the end of 2002, 3 year Key Element technology Phase (KEP) to reduce the key technology risk factors has been completed. This paper describes these KEP tasks results. To evaluate Li flow characteristics, a water and Li flow experiments have been done. To develop Li purification system, evaluation of nitrogen and tritium gettering materials have been done. Conceptual design of remote handling and basic experiment have been donde. In addition, safety analysis and diganostics design have been done. In the presentation, the latest design and future prospects will be also summarized.

Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

Journal Articles

Liquid lithium target under steady state ultra high heat load of 1 GW/m$$^{2}$$ range for International Fusion Materials Irradiation Facility (IFMIF)

Nakamura, Hiroo; Ida, Mizuho*; Nakamura, Hideo; Takeuchi, Hiroshi; IFMIF International Team

Fusion Engineering and Design, 65(3), p.467 - 474, 2003/04

 Times Cited Count:4 Percentile:32.68(Nuclear Science & Technology)

IFMIF is an accelerator-based neutron source for development of fusion materials. The Li target system consists of a target assembly, a Li purification system and various diagnostics. An intense deuterium beam power up to 10 MW in a footprint of 20$$times$$5 cm$$^{2}$$ corresponds to ultra high heat flux up to 1 GW/m$$^{2}$$. To handle such an ultra high heat flux, the high-speed liquid Li flow with a velocity of 20 m/s and a concave flow configuration are necessary. According to thermal-hydraulic analysis, an induced centrifugal force (160 G) under the concave back wall of a radius of 25 cm is sufficient for IFMIF operation. To confirm the hydraulic characteristics of Li flow, water jet experiment has been done. Moreover, validation experiment in Li loop is planned. In addition, to control tritium and impurities such as C, N, O below permissible levels, a cold trap and two hot traps are used. These technologies have similarities in plasma facing components in fusion reactor. In presentation, the IFMIF Li target technology and its application of to the plasma facing component will be discussed.

Journal Articles

Analytical studies on hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Teion Kogaku, 36(11), p.617 - 625, 2001/11

no abstracts in English

Journal Articles

Analytical studies on the hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Cryogenics, 41(8), p.583 - 594, 2001/08

 Times Cited Count:8 Percentile:38.78(Thermodynamics)

no abstracts in English

Journal Articles

Development of B$$_{4}$$C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

Jimbo, Ryutaro*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; *

Journal of the Ceramic Society of Japan, International Edition, 105, p.1179 - 1187, 1997/00

no abstracts in English

Journal Articles

Nonlinear Fokker-Planck analysis of ion temperature in JT-60U hot ion plasma

Yamagiwa, Mitsuru; Koga, J. K.; Ishida, Shinichi

Proc. of 24th European Physical Society Conf. on Controlled Fusion and Plasma Physics, 21A, p.517 - 520, 1997/00

no abstracts in English

Journal Articles

Fusion yield in high-power D-beam injected He$$^{3}$$ plasmas

Yamagiwa, Mitsuru

Plasma Physics and Controlled Fusion, 34(5), p.715 - 723, 1992/00

no abstracts in English

Journal Articles

Hot atom chemistry and fusion reactors

Hot Atom Chemistry, p.501 - 511, 1984/00

no abstracts in English

Journal Articles

Preliminary design of a fusion reactor fuel cleanup system by the palladium alloy membrane method

; Konishi, Satoshi; Naruse, Yuji

Nucl.Technol./Fusion, 3, p.471 - 484, 1983/00

no abstracts in English

Journal Articles

Chemical behaviors of tritium produced by the $$^{6}$$Li(n, $$alpha$$)T reaction in lithium oxide

; Tanaka, Kichizo;

Journal of Inorganic and Nuclear Chemistry, 40(3), p.363 - 367, 1978/03

 Times Cited Count:42

no abstracts in English

Oral presentation

Optimization of condition for invar/stainless HIP diffusion bonding

Wakui, Takashi; Naoe, Takashi; Kogawa, Hiroyuki; Haga, Katsuhiro; Wakai, Eiichi; Takada, Hiroshi; Futakawa, Masatoshi

no journal, , 

The mercury target vessel has large size as 1.3$$times$$1.3$$times$$2.5 m$$^{3}$$. In view of reducing the amount of wastes, we have studied the structure so that the fore part could be separated. The flange is required to have high seal performance less than 1$$times$$10$$^{-6}$$ Pam$$^{3}$$/s. Invar with low thermal expansion is a candidate. Due to its low stiffness, however, the flange may deform when it is fastened by bolts. Practically invar is reinforced with stainless steel where all interface between them has to be bonded completely with the HIP bonding. In this study, we made specimens at four temperatures of 973, 1173, 1373 and 1473 K and conducted tensile tests. The specimen bonded at 973 K had little diffusion layer, and so fractured at the interface. The tensile strength reduced with increasing the temperature, and the reduced amount was about 10 % at 1473 K. The analyzed residual stresses near the interface increased by 50 % at maximum. Then, we concluded that the optimum temperature was 1173 K.

17 (Records 1-17 displayed on this page)
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