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Takeda, Takeshi
JAEA-Data/Code 2016-004, 59 Pages, 2016/07
The TR-LF-07 test simulated a loss-of-feedwater transient in a PWR. A SI signal was generated when steam generator (SG) secondary-side collapsed liquid level decreased to 3 m. Primary depressurization was initiated by fully opening a power-operated relief valve (PORV) of pressurizer (PZR) 30 min after the SI signal. High pressure injection (HPI) system was started in loop with PZR 12 s after the SI signal, while it was initiated in loop without PZR when the primary pressure decreased to 10.7 MPa. The primary and SG secondary pressures were kept almost constant because of cycle opening of the PZR PORV and SG relief valves. The PZR liquid level began to drop steeply following the PORV full opening, which caused liquid level formation at the hot leg. The primary pressure became lower than the SG secondary pressure, which resulted in the actuation of accumulator (ACC) system in both loops. The primary feed-and-bleed operation was effective to core cooling because of no core uncovery.
Lee, C. G.; Iguchi, Kazunari; Esaka, Fumitaka; Magara, Masaaki; Sakurai, Satoshi; Watanabe, Kazuo; Usuda, Shigekazu
Nuclear Instruments and Methods in Physics Research B, 245(2), p.440 - 444, 2006/04
Times Cited Count:8 Percentile:50.27(Instruments & Instrumentation)The etching rates of fission track detectors made of polycarbonate containing uranium particles were measured after thermal neutron irradiation with fluence of 810 n/cm, in order to study the influence of uranium enrichment on the etching rate that was calculated from the weight loss by etching. There is a strong correlation between the etching rate of detector and the enrichment E of uranium particle: the former increases as the latter increases. Particularly, the etching rate per particle was proportional to E rather than E, which is probably due to the overlapping of fission tracks. The etching behaviors of detector revealed that the existence of two different etching rate regions, a nonlinear region in the beginning of etching process and a subsequent constant region, which was explained as the opening of fission tracks and the broadening of opened tracks, respectively.
Urata, Kazuhiro*
JAERI-Data/Code 2003-005, 36 Pages, 2003/03
In design of the fusion devises in which ferritic steel is planned to use as the plasma facing material and/or the inserts for ripple reduction, the appreciation of the error field effect and the optimization of ferritic plate arrangement to reduce the toroidal field ripple require calculation of ferritic magnetic field. However iterative calculations by the non-linearity in B-H curve disturbs high-speed calculation. In the strong toroidal magnetic field in the tokamak, fully magnetic saturation of ferritic steel occurs. Hence a distribution of magnetic charges as magnetic field source is determined straightforward. Additionally objective ferritic steel geometry is limited to the thin plate and they are installed along the toroidal magnetic field. Taking them into account, high-speed calculation code FEMAG has been developed. In this report, the formalization of FEMAG, how to use FEMAG, and the validity check in comparison with a 3D FEM code, with the measurements of the magnetic field in JFT-2M are described. The presented examples are design studies for JT-60 modification.
Murata, Mikio; Kinouchi, Nobuyuki; Yokoyama, Sumi
JAERI-M 94-065, 93 Pages, 1994/03
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
Journal of Nuclear Science and Technology, 27(6), p.535 - 546, 1990/06
no abstracts in English
; ; *; *; ; Murao, Yoshio
JAERI-M 87-002, 77 Pages, 1987/02
no abstracts in English
Ono, Shinichi; ;
Bulletin of the Chemical Society of Japan, 59(6), p.1947 - 1951, 1986/00
Times Cited Count:2 Percentile:25.2(Chemistry, Multidisciplinary)no abstracts in English
; ; *
JAERI-M 85-186, 58 Pages, 1985/11
no abstracts in English
; Murao, Yoshio
JAERI-M 83-091, 108 Pages, 1983/06
no abstracts in English