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Aftereffect of copper mineral nanoparticles and copper mineral ions for the buildings of variety fish olfactory mucosa.
nternational research. These results can provide reference to the effect of ferroptosis on human health with low-dose radiation.
This study examines the nonuniform exposure to the cornea from incident millimeter waves at 94-100 GHz. Two previous studies measured temperature increases in the rhesus cornea exposed to brief (1-6 s) pulses of high-fluence millimeter waves (94 GHz), one of which also estimated thresholds for corneal damage (reported as ED50, the dose resulting in a visible lesion 50% of the time). Both studies noted large variations in the temperature increase across the surface of the cornea due to wave interference effects. This study examines this variability using high-resolution simulations of mm-wave absorption and temperature increase in the human cornea from exposures to plane wave energy at 100 GHz. Calculations are based on an earlier study. The simulations show that the peak temperature increases in the cornea from short exposures (up to 10 s) to high-intensity mm-wave pulses are 1.7-2.8 times the median increase depending on the polarization of the incident energy. A simple one-dimensional "baseline" model proes. The first estimate is based on thresholds for thermal damage from pulsed infrared energy, and the second is based on a thermal damage model. The mm-wave pulses presently considered far exceed current IEEE or ICNIRP exposure limits but may be produced by some nonlethal weapons systems. Interference effects due to wave reflections from structures in and near the eye result in highly localized variations in energy absorbed in the cornea and surrounding facial tissues and are important to consider in a hazard analysis for exposures to intense pulsed millimeter waves.
Dose estimation was conducted by assuming landfill disposal of removed soil generated outside the Fukushima Prefecture by each local town and in a lump sum. Because the radioactivity of removed soil is lower than that of specified waste that was generated at Fukushima Prefecture and the radioactivity concentration is 100,000 Bq kg-1 or less, simple landfill covered with 30 cm of non-contaminated soil was used. The exposure doses of loading/unloading, transportation, and landfill workers and the public residing near the repository site were estimated. Selleck MLN4924 Furthermore, migration of cesium into groundwater because of precipitation and using the contaminated groundwater for drinking and agricultural water was evaluated, and exposure doses regarding farmers and the ingestion of agricultural products were estimated. It was confirmed that estimated exposure doses during landfill were less than 1 mSv y-1, and those for after landfill were 0.01 mSv y-1.
Dose estimation was conducted by assuming landfill disposal of removed soil generated outside the Fukushima Prefecture by each local town and in a lump sum. Because the radioactivity of removed soil is lower than that of specified waste that was generated at Fukushima Prefecture and the radioactivity concentration is 100,000 Bq kg-1 or less, simple landfill covered with 30 cm of non-contaminated soil was used. The exposure doses of loading/unloading, transportation, and landfill workers and the public residing near the repository site were estimated. Furthermore, migration of cesium into groundwater because of precipitation and using the contaminated groundwater for drinking and agricultural water was evaluated, and exposure doses regarding farmers and the ingestion of agricultural products were estimated. It was confirmed that estimated exposure doses during landfill were less than 1 mSv y-1, and those for after landfill were 0.01 mSv y-1.
Yttrium-90 (90Y)-polymer composite (RadioGel™) is a new cancer therapeutic agent for treating solid tumors by direct interstitial injection. The 90Y-composite comprises insoluble, microscopic yttrium-phosphate particles carried by a sterile, injectable water-polymer (hydrogel) solution that can be placed directly by needle injection into solid tumors. The yttrium-90-RadioGel™ agent was designed to provide a safe, effective, localized, high-dose beta radiation for treating solid tumors. The properties of 90Y-RadioGel™ also make it a relatively safe agent for health care personnel who prepare, handle, and administer the material. The purpose of this work was to demonstrate and characterize radiation safety of the injectable 90Y-RadioGel™ therapeutic agent. Safety in the patient is defined by its ability to target precisely and remain confined within tumor tissue so that radiation doses are imparted to the tumor and not to normal organs and tissues. Radiation safety for health care personnel is defined by the counting at 48 h post-injection of tumors or margins with 90Y-RadioGel™ showed that significant radioactivity was measurable only at the site of administration and that radioactivity above detector background was not found in blood or peripheral organs and tissues. At 10 d post-injection, microCT showed that yttrium phosphate microparticles were confined to the injection site. Yttrium-90 remained where placed and did not migrate away in significant amounts from the injection site. Radiation doses were confined mainly to tumors and margin tissues. During preparation and administration, radiation doses to hands and body of study personnel were negligible. This work showed that 90Y-RadioGel™ can be safely prepared and administered and that radiation doses to cancer patients are confined to tumor and margin tissues rather than to critical normal organs and tissues.
This paper describes how environmental measurement data were used to help quantify the spatial impact and behavior of uranium released to the environment from a uranium manufacturing facility in Apollo, PA. The Apollo facility released enriched uranium to the environment while it operated between 1957 and 1983. Historical monitoring data generated by the site, along with other independent data sources, provided a long-term record documenting the presence and behavior of uranium in the local environment. This record of evidence, together with reconstructed estimates of facility releases, has been used to estimate environmental concentrations during facility operations and potential exposures to members of the public. Historical environmental measurement data were also used to confirm predictions of deposition and concentrations in air. The data are used here to derive atmospheric deposition velocities for the uranium emissions. Based on the spatial pattern of measurements and calculated deposition velocities around the facility, the released material contained larger particles that deposited close to the facility, and the released material remains largely in the surface layers of the soil, indicating limited downward mobility.
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