يعرض 1 - 10 نتائج من 68 نتيجة بحث عن '"Kowatari, Munehiko"', وقت الاستعلام: 1.20s تنقيح النتائج
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    دورية أكاديمية
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    دورية أكاديمية
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    دورية أكاديمية

    المصدر: JAAS (Journal of Analytical Atomic Spectrometry); Dec2023, Vol. 38 Issue 12, p2562-2570, 9p

    مصطلحات جغرافية: FRANCE

    مستخلص: It is critical to perform dose assessment after internal contamination with beta-particle emitting 90Sr due to its relatively long physical and biological half-lives, along with the higher specific activities of 90Sr and its daughter 90Y. For rapid public screening after a large-scale radiological/nuclear accident, we developed a novel 90Sr bioassay for small-volume urine samples using triple-quadrupole inductively coupled plasma-mass spectrometry (ICP-MS/MS). After organic matter decomposition of 10 mL urine using HNO3, stacked DGA and Sr resin cartridges were used directly for chromatographic separation and purification of Sr. Yields of Sr were measured as 94 ± 5% (n = 12) for the whole procedure, using stable 88Sr originally in the urine sample as a yield tracer. CO2 proved to be a better reaction gas than O2, to overcome isobaric/polyatomic interferences, especially those caused by Zr and Ge. With a conventional introduction system + s lens + 75% CO2 flow rate in the 4# cell gas line, the method detection limit (MDL) was estimated to be 0.978 pg L−1 (5 Bq L−1) in 10 mL urine, meeting the public screening requirement for judging ingestion/inhalation exposure beyond 1 mSv Committed Effective Dose Equivalent, with a reasonable throughput (∼6 h for 12 samples). For method validation, the standard reference materials provided by PROCORAD (Association for the PROmotion of Quality COntrol in RADiotoxicological Analysis), France, were analyzed and the results were all in good agreement with the assigned values. [ABSTRACT FROM AUTHOR]

    : Copyright of JAAS (Journal of Analytical Atomic Spectrometry) is the property of Royal Society of Chemistry and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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    دورية أكاديمية

    المصدر: Radiation Protection Dosimetry; Oct2023, Vol. 199 Issue 15, p1774-1778, 5p

    مستخلص: Chronic radiation exposure increases the risk of skin damage of medical personnel engaged in radiology. However, hand dose measurements in computed tomography (CT) for diagnostic purposes have not been evaluated. The occupational radiation dose to the hands of CT assistants was herein investigated to evaluate its compliance with the equivalent dose limit for the hand (500 mSv/year). The occupational doses of nine CT assistants were measured in 89 cases (April 2017–May 2018) by installing radio-photoluminescence glass dosemeters (GD-302 M) (70-μm dose-equivalent conversion coefficient = 0.37) on the dorsal aspect of both hands. The occupational dose to the hand was the highest with head holding (right: 1.14 mSv/CT scan, left: 1.07 mSv/CT scan). Considering the results for annual work, even for head holding, the hand dose of the CT-assisting personnel was insignificant. However, CT assistants should be mindful of the possibility of locally higher doses to hands. [ABSTRACT FROM AUTHOR]

    : Copyright of Radiation Protection Dosimetry is the property of Oxford University Press / USA and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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    دورية أكاديمية

    المصدر: Radiation Protection Dosimetry; Oct2023, Vol. 199 Issue 15, p1994-1999, 6p

    مستخلص: To provide timely information for prompting decision-making in emergency radiation therapy, we developed simple and rapid mass and alpha spectrometric methods for urinary bioassays to determine ultra-trace actinide isotopes. For the mass spectrometric method, after organic matter decomposition, LaF3/CaF2 co-precipitation and chromatographic purification using 2 ml of AG MP-1 M anion exchange resin, U and Pu isotopes were measured in a 20-ml urine sample by inductively coupled plasma-mass spectrometry. In the alpha spectrometric method, after organic matter decomposition, iron hydroxide co-precipitation and chromatographic purification using 2 ml of TEVA and 2 ml of DGA resin cartridges, Pu, U and Am/Cm isotopes were measured in a 500-ml urine sample by alpha spectrometry. These alpha and mass spectrometric methods were then applied for participation in the 2020 intercomparison organized by the Association for the PROmotion of Quality COntrol in RADiotoxicological Analysis (PROCORAD), France, for method validations. [ABSTRACT FROM AUTHOR]

    : Copyright of Radiation Protection Dosimetry is the property of Oxford University Press / USA and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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    دورية أكاديمية

    المصدر: Radiation Protection Dosimetry; Oct2023, Vol. 199 Issue 15, p1848-1852, 5p

    مصطلحات جغرافية: JAPAN

    الشركة/الكيان: LAWRENCE Livermore National Laboratory

    مستخلص: A new in-vivo counting system that functions as both a whole-body counter (WBC) and a lung counter (LC) was developed at the QST to enhance its dose assessment capability. This paper presents an overview of this system and the results of its performance tests. For use of the system as a WBC, three high purity germanium (HPGe) detectors installed in a 20-cm-thick iron shielding chamber are linearly arrayed over a subject lying on the bed, whereas two of the three HPGe detectors are placed over the subject's chest from side to side when using the system as an LC. The new in-vivo system was calibrated using three de-facto phantoms owned by the QST: an adult-male BOttle Manikin ABsorption (BOMAB) phantom, a Lawrence Livermore National Laboratory (LLNL) phantom and a Japan Atomic Energy Research Institute (JAERI) phantom. Monte Carlo simulations were also performed to determine an optimum location for the three detector array in the WBC mode and revealed that the peak efficiency for the BOMAB phantom (662 keV) was little varied as long as the middle detector was placed above the thorax and abdomen parts of the phantom. The calculated peak efficiencies agreed well with the observed peak efficiencies for photons with energies over 100 keV. For lung counting, a tentative Minimum Detectable Activity of 241Am was evaluated as 9.5 Bq for a counting time of 30 minutes, and a Japanese male subject with an average chest wall thinness (2.27 cm). The developed system is now ready for use. [ABSTRACT FROM AUTHOR]

    : Copyright of Radiation Protection Dosimetry is the property of Oxford University Press / USA and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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    دورية أكاديمية

    المصدر: Radiation Protection Dosimetry; Oct2023, Vol. 199 Issue 15, p2020-2024, 5p

    مصطلحات جغرافية: JAPAN

    مستخلص: Japan's National Institutes for Quantum Science and Technology (QST) was designated as the core radiation emergency medical support center by the country's Nuclear Regulation Authority (NRA) in 2019. One of the main missions of the QST is to maintain and improve its dose assessment capability for radiation-exposed individuals. Toward the goal of effectively fulfilling this mission, a new facility—the Dose Assessment Building for Advanced Radiation Emergency Medicine—was constructed at the Chiba base of the QST in 2020. An integrated bioassay laboratory was installed in this facility for assessing subjects' internal doses, along with a new integrated in vivo counter. The bioassay capability of the new laboratory is currently expected to screen 5–10 persons simultaneously assuming internal contamination with actinides such as Pu, Am/Cm and U, although this is dependent on the specific contamination circumstances. [ABSTRACT FROM AUTHOR]

    : Copyright of Radiation Protection Dosimetry is the property of Oxford University Press / USA and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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    دورية أكاديمية
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    دورية أكاديمية

    المساهمون: Japan Society for the Promotion of Science

    المصدر: Journal of Analytical Atomic Spectrometry ; volume 38, issue 12, page 2562-2570 ; ISSN 0267-9477 1364-5544

    الوصف: Further mitigation: CO 2 is a better reaction gas than O 2 to overcome isobaric/polyatomic interferences caused by Zr and Ge for 90 S analysis by ICP-MS/MS. The method detection limit was 0.978 pg L −1 (5 Bq L −1 ) in 10 mL urine, with a reasonable throughput (∼6 h for 12 samples).

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    دورية أكاديمية

    المساهمون: Ministry of Health, Labour and Welfare, Japan

    المصدر: Radiation Protection Dosimetry ; volume 199, issue 11, page 1239-1247 ; ISSN 0144-8420 1742-3406

    الوصف: We performed an experimental investigation on occupational exposure of the eye lens and the extremity of radiation workers engaged in handling of highly activated materials in a small research accelerator facility. Using a simplified physical phantom to simulate the relevant inhomogeneous radiation exposure situations, the personal dose equivalents obtained at the eye lens and the extremities of radiation workers handling heavily radioactive converters were measured together with the dose measured by personal dosemeters worn on their trunk. Results of mockup experiments and the Monte Carlo calculations suggest that the quantitative estimation of the eye lens doses can be estimated from the trunk dose, while the extremity doses vary considerably from the dose readings from the trunk, depending on the use of simple point-source or volume source geometry.