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1.
J Environ Radioact ; 139: 308-319, 2015 Jan.
Artículo en Inglés | MEDLINE | ID: mdl-24703526

RESUMEN

Soil deposition density maps of gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident were constructed on the basis of results from large-scale soil sampling. In total 10,915 soil samples were collected at 2168 locations. Gamma rays emitted from the samples were measured by Ge detectors and analyzed using a reliable unified method. The determined radioactivity was corrected to that of June 14, 2011 by considering the intrinsic decay constant of each nuclide. Finally the deposition maps were created for (134)Cs, (137)Cs, (131)I, (129m)Te and (110m)Ag. The radioactivity ratio of (134)Cs-(137)Cs was almost constant at 0.91 regardless of the locations of soil sampling. The radioactivity ratios of (131)I and (129m)Te-(137)Cs were relatively high in the regions south of the Fukushima NPP site. Effective doses for 50 y after the accident were evaluated for external and inhalation exposures due to the observed radioactive nuclides. The radiation doses from radioactive cesium were found to be much higher than those from the other radioactive nuclides.


Asunto(s)
Accidente Nuclear de Fukushima , Monitoreo de Radiación , Ceniza Radiactiva/análisis , Radioisótopos/análisis , Contaminantes Radiactivos del Suelo/análisis , Mapeo Geográfico , Japón , Plantas de Energía Nuclear
3.
Radiat Prot Dosimetry ; 115(1-4): 623-9, 2005.
Artículo en Inglés | MEDLINE | ID: mdl-16381795

RESUMEN

Precise estimation of induced activities in concrete shields for high-energy accelerator facilities is one of the most important issues that need to be solved, not only for the reduction of exposure for workers, but also for the reduction of radioactive wastes. Irradiation experiments have been performed by using the 500 MeV Neutron Spallation Source Facility in KEK. The large concrete assembly was placed in the direction of 0 degrees to the beamline. Two kinds of samples were placed at several positions in the assembly. The irradiation period was about 1 week and induced activities in the samples were measured until approximately 1.5 y after irradiation. From the comparison between the experiment and the available Monte Carlo calculation code system, good agreement was obtained for 24Na, 47Sc, 47Ca and 54Mn within a factor 2; however, large discrepancies were observed for some other nuclides.


Asunto(s)
Materiales de Construcción/análisis , Transferencia Lineal de Energía , Neutrones , Aceleradores de Partículas/instrumentación , Protección Radiológica/instrumentación , Radiometría/métodos , Simulación por Computador , Análisis de Falla de Equipo , Ensayo de Materiales , Modelos Estadísticos , Dosis de Radiación , Protección Radiológica/métodos
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