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Kasugai, Yoshimi; Harada, Masahide; Kai, Tetsuya; Oi, Motoki; Meigo, Shinichiro; Maekawa, Fujio
JAEA-Data/Code 2015-033, 28 Pages, 2016/03
The high-energy neutron fluxes and spectra around the mercury spallation neutron source at MLF of J-PARC were measured by the multi-foil activation method. The threshold energies of neutron reactions utilized in this experiment covered from 0.1 to 50 MeV. The foil irradiation was carried out on the first beam-run of MLF from May 30th to 31th, 2008. After the irradiation, the induced radioactivity of each foil was measured using an HPGe detector, and the neutron-induced reaction-rate distribution around the mercury target was determined. Using these data, the high-energy neutron fluxes and spectra were deduced with unfolding method in which the neutron spectra calculated with PHITS code were used as the initial-guess spectra. By comparison between the initial and the unfolded spectra, it was shown that most of the calculation results, which had been the basis of the neutronics design of the MLF target assembly, were consistent with the experimental data within 30%.
Konovalov, S. V.; Mikhailovskii, A.*; Ozeki, Takahisa; Takizuka, Tomonori; Shirokov, M. S.*; Hayashi, Nobuhiko
Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11
Influence of anomalous perpendicular heat transport and anomalous perpendicular viscosity on conditions of Neoclassical Tearing Mode onset is studied theoretically. Series of different parallel transport mechanisms competitive to anomalous cross-island heat conductivity in the perturbed temperature profile are considered.In the transport threshold model, magnetic curvature effect is as much important as bootstrap drive weakened by the finite perpendicular heat transport. Perpendicular viscosity brings island-rotation-frequency dependence of the transport threshold model.
Takizuka, Tomonori; ITPA H-mode Threshold Database Working Group*
Plasma Physics and Controlled Fusion, 46(5A), p.A227 - A233, 2004/05
Times Cited Count:57 Percentile:84.43(Physics, Fluids & Plasmas)To evaluate the H-mode power threshold in future tokamak reactors, quantitative scaling formulas have been developed by using the ITPA threshold database. Recently data from spherical tokamaks (MAST and NSTX) were supplied to the ITPA database. A new scaling expression, which includes the absolute magnetic field B instead of the toroidal magnetic field, subsumes the plasma current dependence at low aspect ratio and is consistent with the previous data without any explicit current dependence. Other possible influence of the low aspect ratio to increase the power threshold is also investigated. It is cralified for the whole data set that the effective charge number Z raises the power threshold. By adding Z as a parameter of the scaling expression, both the scattering nature and the low-density anomaly found in the experimental data can be reduced.
Nakamura, Takehiko*; Fuketa, Toyoshi; Sugiyama, Tomoyuki; Sasajima, Hideo
Journal of Nuclear Science and Technology, 41(1), p.37 - 43, 2004/01
Times Cited Count:19 Percentile:75.17(Nuclear Science & Technology)Transient deformation of high burnup BWR fuel rods was measured and failure limit was examined under simulated RIA conditions. Brittle cladding failure occurred at a small strain of about 0.4% during an early phase of the pulse irradiation tests at the NSRR. Strain rates were in an order of tens %/s at the time of the failure. Comparison of the results with thermal expansion of pellets suggested that the deformation was caused by thermal expansion of the pellets. In other words, the influence of fission gases in the pellets was small in the early phase of the deformation. Separate effect tests were conducted to examine influence of the cladding temperature on the failure behavior of cladding. Influence of the pulse width on the failure threshold was discussed in terms of the strain rate, magnitude of the deformation and temperature of the cladding for high burnup BWR fuel rods under RIA conditions.
Mikhailovskii, A. B.*; Shirokov, M. S.*; Tsypin, V. S.*; Konovalov, S. V.; Ozeki, Takahisa; Takizuka, Tomonori; Galvo, R. M. 0.*; Nascimento, I. C.*
Physics of Plasmas, 10(10), p.3975 - 3983, 2003/10
Times Cited Count:8 Percentile:25.78(Physics, Fluids & Plasmas)A transport threshold model of subsonic neoclassical tearing modes (NTMs) in tokamaks is developed. The basic procedure is to include the velocity-dependent term into the single-fluid heat-conductivity equation. and to supply the parallel plasma motion equation. These equations permit the determination of the perturbed plasma temperature and the bootstrap current drive of NTMs, for both strong and weak perpendicular heat transport. It is shown that the subsonic NTMs transport threshold model can be more realistic than the standard transport threshold model of NTMs.
Mikhailovskii, A. B.*; Shirokov, M. S.*; Tsypin, V. S.*; Konovalov, S. V.*; Ozeki, Takahisa; Takizuka, Tomonori; Galvo, R. M. 0.*; Nascimento, I. C.*
Physics of Plasmas, 10(9), p.3790 - 3792, 2003/09
Times Cited Count:5 Percentile:16.93(Physics, Fluids & Plasmas)A fluid treatment of convective-transport threshold model of neoclassical tearing modes (NTMs) in tokamaks is developed. A system of moment equations of the drift kinetic equation with a model perpendicular transport is derived. The essence of this moment equation system is to allow for the parallel heat flux on an equal footing with pressure and temperature. The suggested moment equation system is applied for analyzing the bootstrap current drive of NTMs. As a result, a threshold model of these modes is derived, which coincides qualitatively with the convective-transport threshold model initially formulated by means of intuitive consideration.
Yamashita, Toshiyuki; Kuramoto, Kenichi; Akie, Hiroshi; Nakano, Yoshihiro; Shirasu, Noriko; Nakamura, Takehiko; Kusagaya, Kazuyuki*; Omichi, Toshihiko*
Journal of Nuclear Science and Technology, 39(8), p.865 - 871, 2002/08
Times Cited Count:25 Percentile:81.45(Nuclear Science & Technology)Research on the plutonium rock-like oxide (ROX) fuels and their once-through burning in light water reactors has been performed to establish an option for utilizing and disposing effectively the excess plutonium. The ROX fuel is a sort of the inert matrix fuels and consists of mineral-like compounds such as yttria stabilized zirconia, spinel and corundum. A particle-dispersed fuel was devised to reduce damage by heavy fission fragments. Some preliminary results on swelling, fractional gas release and microstructure change for five ROX fuels were obtained from the irradiation test and successive post-irradiation examinations. Inherent disadvantages of the Pu-ROX fuel cores could be improved by adding 238U or 232Th as resonant materials, and all improved cores showed a nearly the same characteristics as the conventional UO2 core during transient conditions. The threshold enthalpy of the ROX fuel rod failure was found to be comparable to the fresh UO2 rod by pulse-irradiation tests simulating reactivity initiated accident conditions.
Kameo, Yutaka; Nakashima, Mikio; Hirabayashi, Takakuni*
Nuclear Technology, 137(2), p.139 - 146, 2002/02
Times Cited Count:7 Percentile:44.29(Nuclear Science & Technology)In order to apply laser ablation technique for decontamination of metal wastes contaminated with radioactive nuclides, the effect of irradiation atmospheres on removal of oxide layers on steel surfaces by laser ablation was studied. Based on the assumption that the absorption of laser light follows the Lambert-Beer law, ablation parameters, such as absorption length and threshold fluence for ablation, of sintered FeO and stainless and carbon steels were measured in He, O, Kr or SF atmosphere. The results indicated that SF was the most effective gas of all irradiation atmospheres studied for the exclusive removal of oxide layers formed on stainless and carbon steel samples in high temperature pressurized water. Secondary ion mass spectroscopic measurement and scanning electron microscopic observation confirmed that no oxide layer existed on the steel samples after the exclusive removal with laser irradiation.
Miura, Yukitoshi
Purazuma, Kaku Yugo Gakkai-Shi, 74(9), p.968 - 976, 1998/09
no abstracts in English
Miura, Yukitoshi; *; *; Hoshino, Katsumichi; *; *; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.
Fusion Energy 1996, p.167 - 175, 1997/05
no abstracts in English
Kasugai, Yoshimi; Ikeda, Yujiro; Yamamoto, Hiroshi*; Kawade, Kiyoshi*
Annals of Nuclear Energy, 23(18), p.1429 - 1444, 1996/00
Times Cited Count:24 Percentile:86.64(Nuclear Science & Technology)no abstracts in English
Ryter, F.*;
Nuclear Fusion, 36(9), p.1217 - 1264, 1996/00
Times Cited Count:123 Percentile:94.76(Physics, Fluids & Plasmas)no abstracts in English
V.M.Maslov*;
Nuclear Science and Engineering, 124(3), p.492 - 497, 1996/00
Times Cited Count:7 Percentile:54.39(Nuclear Science & Technology)no abstracts in English
Katanishi, Shoji; Ishijima, Kiyomi
Journal of Nuclear Science and Technology, 32(11), p.1098 - 1107, 1995/11
Times Cited Count:2 Percentile:28.04(Nuclear Science & Technology)no abstracts in English
JAERI-Conf 95-010, 34 Pages, 1995/06
no abstracts in English
M.Hoek*; Nishitani, Takeo; Ikeda, Yujiro; Morioka, Atsuhiko
Review of Scientific Instruments, 66(1), p.885 - 887, 1995/01
Times Cited Count:23 Percentile:83.34(Instruments & Instrumentation)no abstracts in English
Tanzawa, Sadamitsu; ;
Journal of Nuclear Science and Technology, 30(4), p.281 - 290, 1993/04
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English
Kardaun, O.*; Ryter, F.*; Stroth, U.*; Kus, A.*; Deboo, J. C.*; Schissel, D. P.*; Bramson, G.*; Carlstrom, T. N.*; Thomsen, K.*; Campbell, D. J.*; et al.
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.3, p.251 - 270, 1993/00
no abstracts in English
Yanagisawa, Kazuaki; ; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo
Proc. of the 16th RERTR Meeting, 16 Pages, 1993/00
no abstracts in English
Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo
Nihon Genshiryoku Gakkai-Shi, 34(9), p.879 - 888, 1992/09
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English