Journal ArticleDOI
A simple mass and heat balance model for estimating plant conditions during the Fukushima Dai-ichi NPP accident
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TLDR
A simple evaluation method for the analysis of thermal-hydraulic transients in reactor pressure vessel (RPV) and primary containment vessel (PCV) is proposed to support understanding the accident in this paper.Abstract:
A simple evaluation method for the analysis of thermal-hydraulic transients in reactor pressure vessel (RPV) and primary containment vessel (PCV) is proposed to support understanding the accident b...read more
Citations
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Journal ArticleDOI
Fiber-optic laser-induced breakdown spectroscopy of zirconium metal in air: Special features of the plasma produced by a long-pulse laser
Ayumu Matsumoto,Hironori Ohba,Masaaki Toshimitsu,Katsuaki Akaoka,Alexandre Ruas,Tetsuo Sakka,Ikuo Wakaida +6 more
TL;DR: In this article, the emission spectra of zirconium metal in air obtained for a normal-pulse laser (6 ns) and a longpulse (100 ns) (wavelength: 1064nm, pulse energy: 12.5mJ, spot diameter: 0.35mm) were compared to investigate the fundamental aspects of fiber-optic LIBS with the long-Pulse laser.
Proceedings ArticleDOI
First Experiments at the CIGMA Facility for Investigations of LWR Containment Thermal Hydraulics
Proceedings ArticleDOI
Telemetry System for 2D Flow Map using Ultrasonic Velocity Profiler
Zeliang Zhang,Naruki Shoji,Munkhbat Batsaikhan,Hideharu Takahashi,Wongsakorn Wongsaroj,Hiroshige Kikura +5 more
TL;DR: In this article, the authors proposed a remote detection method for the decommissioning of the Fukushima Daiichi Nuclear Power Plant (FDNPP), which combines robot and measurement technique.
Journal ArticleDOI
Recent activities in the field of thermal hydraulic researches
Qiusheng Liu,Shinichi Morooka +1 more
TL;DR: In this article, the effects of spacer grids on the single-phase convection heat transfer enhancement were investigated, and it was found that a second-stage augmentation occurs under wet grid conditions at a distance of 10 diameters downstream of the grid.
References
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TRAC-BF1/MOD1: An advanced best-estimate computer program for BWR accident analysis, Model description. Volume 1
J.A. Borkowski,N.L. Wade,M.M. Giles,S.Z. Rouhani,R.W. Shumway,G.L. Singer,D.D. Taylor,W.L. Weaver +7 more
TL;DR: The Transient Reactor Analysis Code (TRAC) as discussed by the authors provides a best-estimate analysis capability for analyzing the full range of postulated accidents in boiling water reactor (BWR) systems and related facilities.
ReportDOI
A simplified model of decontamination by BWR steam suppression pools
TL;DR: In this article, a simplified model of decontamination by steam suppression pools is developed by correlating features of the uncertainty distributions for total decentamination factor, DF(total), mean size of emerging aerosol particles, d{sub p, and the standard deviation of themore ǫ, with pool depth.
Steam explosion simulation code JASMINE v.3 user's guide
TL;DR: In this article, a mechanistic steam explosion simulation code, JASMINE, was developed for plant scale assessment of the steam explosion loads, which is applicable to plant-scale assessment of steam explosion load.