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Uwaba, Tomoyuki; Ito, Masahiro*; Ishitani, Ikuo*
JAEA-Technology 2023-006, 36 Pages, 2023/05
JAEA-Technology-2023-006.pdf:3.45MB
The BAMBOO code developed by the Japan Atomic Energy Agency is a computer code to analyze fuel pin bundle deformation in a fast reactor wire-spaced type fuel pin bundle subassembly. In this study we developed an analysis model to consider friction at the contact points between adjacent fuel pins, and at these between outermost fuel pins and a duct that are due to bundle-duct interaction. This model deals with friction forces at contact points in the contact and separation analysis of the code, and employs a convergent calculation where contact forces are gradually determined to avoid numerical instability when the friction occurs. Analyses of BAMBOO with the model showed very slight effects on the onset of contact between outer most pins and a duct, and on directions of pin displacements, within the range of practical friction coefficients.
Dost
l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; Amaya, Masaki; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10
Ozawa, Kazumi; Tanigawa, Hiroyasu; Morisada, Yoshiaki*; Fujii, Hidetoshi*
Fusion Engineering and Design, 98-99, p.2054 - 2057, 2015/10
Times Cited Count：1 Percentile：9.71(Nuclear Science & Technology)Reduced activation ferritic/martensitic steel, as typified by F82H, is a promising candidate for structural material of DEMO fusion reactors. To prevent plasma sputtering, tungsten (W) coating was essentially required. This study aims to examine the irradiation effects on hardness and microstructure of vacuum-plasma-spray coated W-F82H steel, with a special emphasis on the impacts of grain-refining induced by frictional stir processing (FSP). It was revealed that the hardness of the VPS-FSP W after ion-irradiation to 5.4 dpa at 800
C were not remarkably changed, where bulk W usually exhibited significant irradiation hardening.
Al cable-in-conduit conductor under electromagnetic force; Relation between pressure drop characteristics and cable stiffnessHamada, Kazuya; Matsui, Kunihiro; Takahashi, Yoshikazu; Nakajima, Hideo; Kato, Takashi; CS Model Coil Test Group
Teion Kogaku, 38(8), p.417 - 424, 2003/08
As one of the R&D of ITER. a hydraulic performance of NbAl insert coil was measured and compared with other NbSn conductors. It seems that a longer twist pitch will promote a triangle helium flow space among 4th twist stage cables, jacket and center channel and contribute reduction of pressure drop. Under 500 kN/m of the electromagnetic force, the pressure drop of the NbAl insert decreased by approximately 5%. NbAl conductor indicated quit rigid characteristic under the electromagnetic force and suitable for future magnet with higher magnetic field and current.
Abe, Tetsuya; Kanari, Moriyasu; Tanzawa, Sadamitsu; Hiroki, Seiji
JAERI-Tech 2002-093, 17 Pages, 2002/12
JAERI-Tech-2002-093.pdf:3.04MB
no abstracts in English
Hamada, Kazuya; Kawano, Katsumi; Matsui, Kunihiro; Kato, Takashi; Sugimoto, Makoto; Hara, Eiji*; Okuno, Kiyoshi; Egorov, S. A.*; Rodin, I.*; Sytnikov, V. E.*; et al.
Teion Kogaku, 37(10), p.531 - 538, 2002/10
In the Engineering Design Activities of the International Thermonuclear Experimental Reactor (ITER), Toroidal Field (TF) Insert have been developed and tested successfully. In the experiment, pressure drop performance of TF insert was investigated. There were two purposes for the investigation. One is to verify the pressure drop prediction using correlations proposed by various researchers. Second is to observe a behavior of pressure drop under the electromagnetic force. The pressure drops of TF insert decreased by around 12% during current-carrying operation of 46kA at 13T. After several current-carrying operation, the friction factor of TF insert has finally reached a value which is around 12% lower than that of virgin state and was not recovered even if there were zero current. It is considered that a deformation of cable cross section inside the conductor jacket appears due to electromagnetic force and a new flow path in the jacket is generated.
Hamada, Kazuya; Kato, Takashi; Kawano, Katsumi; Hara, Eiji*; Ando, Toshinari; Tsuji, Hiroshi; Okuno, Kiyoshi; Zanino, L.*; Savoldi, L.*
AIP Conference Proceedings 613, p.407 - 414, 2002/00
no abstracts in English
Ishiyama, Shintaro; Muto, Yasushi; Ogata, Hiroshi*; Kamito, Yoshimi*
Nihon Genshiryoku Gakkai-Shi, 43(7), p.708 - 717, 2001/07
Times Cited Count：3 Percentile：27.07(Nuclear Science & Technology)no abstracts in English
Kaji, Yoshiyuki; Kikuchi, Kenji; Penkalla, H. J.*
Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.179 - 183, 2001/06
A creep constitutive equation in Alloy800H was developed at 700, 800 and 850oC. In the equation, the inelastic strain rate is written in the form of a flow equation of the Norton-Bailey type and the hardening during deformation under various loads is induced by an internal stress which is subdivided into back stress and friction stress. The back stress represents a conservative part of the creep resistance while the friction stress includes all the dissipative parts in the internal structure such as grain boundary sliding, diffusion and interaction between dislocation and precipitation. Parameters were determined by the deformation properties for creep under constant stress conditions at each temperature. Deformation analyses show a good agreement between calculations and experimental results for creep tests at each temperature.
Hamada, Kazuya; Kawano, Katsumi; Hara, Eiji*; Kato, Takashi; Shimba, Toru*; CS Model Coil Test Group
Teion Kogaku, 36(6), p.330 - 335, 2001/06
no abstracts in English
Shibamoto, Yasuteru; Kukita, Yutaka*; Yonomoto, Taisuke; Anoda, Yoshinari
Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.374 - 380, 2000/00
no abstracts in English
Kaminaga, Masanori; Kinoshita, Hidetaka; Haga, Katsuhiro; Hino, Ryutaro; Sudo, Yukio
JAERI-Tech 99-051, 56 Pages, 1999/07
no abstracts in English
*; Kukita, Yutaka*; Tsuji, Yoshiyuki*
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 1, p.40 - 47, 1997/00
no abstracts in English
*; Tsuji, Yoshiyuki*; *; Nakamura, Hideo; ; Kukita, Yutaka
Nihon Genshiryoku Gakkai-Shi, 39(8), p.669 - 680, 1997/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Nakamura, Hideo
JAERI-Research 96-022, 135 Pages, 1996/05
JAERI-Research-96-022.pdf:3.86MB
no abstracts in English
Inagaki, Yoshiyuki; *; Ioka, Ikuo;
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.633 - 637, 1996/00
no abstracts in English
Nakamura, Hideo; Kukita, Yutaka; *
Journal of Nuclear Science and Technology, 32(9), p.868 - 879, 1995/09
Times Cited Count：4 Percentile：43.23(Nuclear Science & Technology)no abstracts in English
; Abe, Yutaka*; Onuki, Akira; Murao, Yoshio
JAERI-Data/Code 94-006, 40 Pages, 1994/07
JAERI-Data-Code-94-006.pdf:1.26MB
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
Journal of Nuclear Science and Technology, 29(3), p.223 - 232, 1992/03
no abstracts in English
; Hino, Ryutaro; Takase, Kazuyuki
Transport Phenomena Science and Technology 1992, p.690 - 695, 1992/00
no abstracts in English
