Showing 41 - 60 results of 281 for search '"radioactivity"', query time: 0.06s Refine Results
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    Monitoring of specific activities of long-lived radioactive elements along the Mini- Okoro/Oginigba Creek, Port Harcourt by Gregory O Avwiri, Olanrewaju Lawal, Edith I Nwokeoji

    Published 2016-05-01
    “…This  study examined the associations and differences  among soil, sediment and water specific activities of long-lived radioactive element (LLRE). Gamma spectroscopy was used to measure the concentration of  the LLRE along the Mini Okoro/Oginigba Creek, Port Harcourt. …”
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    Article
  3. 43

    Reducing the Radioactive Surface Contamination Level of Cobalt-60-Contaminated Material with PVA-Glycerol-EDTA Combination Gel by Rezky Anggakusuma, Gemilang Lara Utama, Muhammad Khoirul Zain, Kartini Megasari

    Published 2025-01-01
    “…The formed gel was applied to the material contaminated by Co-60 with a radioactivity of 81 µCi, as much as 5 µL. The decontamination radioactive efficiency test results range from 53% to 98%, with the highest decontamination efficiency observed on glass media. …”
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  4. 44

    NaI(Tl) Detector Efficiency Computation Using Radioactive Parallelepiped Sources Based on Efficiency Transfer Principle by Mohamed S. Badawi, Mona M. Gouda, Ahmed M. El-Khatib, Abouzeid A. Thabet, Ahmed A. Salim, Mahmoud I. Abbas

    Published 2015-01-01
    “…In this work, the calculations of FEPE are based on computing the effective solid angle ratio between a radioactive point and parallelepiped sources located at various distances from the detector surface. …”
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    Thermal Conductivity of Compacted GO-GMZ Bentonite Used as Buffer Material for a High-Level Radioactive Waste Repository by Yong-Gui Chen, Xue-Min Liu, Xiang Mu, Wei-Min Ye, Yu-Jun Cui, Bao Chen, Dong-Bei Wu

    Published 2018-01-01
    “…In China, Gaomiaozi (GMZ) bentonite serves as a feasible buffer material in the high-level radioactive waste (HLW) repository, while its thermal conductivity is seen as a crucial parameter for the safety running of the HLW disposal. …”
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  6. 46

    Multilayer Shielding Design for Intermediate Radioactive Waste Storage Drums: A Comparative Study between FLUKA and QAD-CGA by Wenqian Li, Xuegang Liu, Ming Li, Yilin Huang, Sheng Fang

    Published 2019-01-01
    “…To ensure that the outside dose rate of waste package is below the limitation of national laws and regulations, based on the standard 200L drum, a new drum with inner shielding was proposed for intermediate-level radioactive waste (ILW) storage. For comparison, FLUKA and QAD-CGA were used to verify the shielding design of the ILW storage drums produced in INET with multiple inner shielding layers. …”
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    Radioactivity concentration of 14C in the air of 14C urea breath test rooms and the resulting internal dose to medical staff by Bei Yu, Fei Chen, Jing Cao, Dingxin Long

    Published 2025-02-01
    “…Objective: To monitor the radioactivity concentration of 14C in the air of rooms used to perform 14C urea breath tests, and evaluate the contamination status of 14C released during such tests, and assess the occupational health risk to medical staff working in such areas. …”
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