Performance of NaI(Tl) detector for gamma-ray spectroscopy

Akkurt, I.; WAHEED, Faez; Akyıldırım, Hakan; Günoğlu, Kadir

doi:10.1007/s12648-021-02210-1

Cited by 13 publications

(6 citation statements)

References 25 publications

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“…The frequent dense material used to attenuate the gamma rays is lead [4,5]. In this study the radiation shielding properties of Boron carbide (B4C) powders have been tested experimentally, using a gamma spectroscopy system containing NaI (TI) detector [6,7,8].…”

Section: Methodsmentioning

confidence: 99%

Experimental Testing of the Radiation Shielding Properties for Steel

WAHEED¹

2022

International Journal of Computational and Experimental Science and Engineering

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Due to the development of nuclear technology and use of technologies in various fields of industry, medicine, and research makes it part of our life. Thus protection against ionizing radiation is one of the most important topics in this field as exposure to gamma radiation is leading to several health effects as the result of absorption by the human body. The purpose of this work is to develop special steel and to measure their radiation shielding properties. The frequently used shielding material for gamma rays is lead. In spite of its effectiveness and high mass attenuation coefficient, lower weight gamma shielding materials are required. In this study we measured radiation shielding properties of some steels using a gamma spectroscopy system containing NaI(TI) detector. The linear attenuation coefficients (μ) for the metal matrix composites (for the steel composites including B4C fractions of 0%, 10% and 20% ) have been calculated at photon energies of 1 kev to 100 Gev using the XCOM online calculation methods, and the experimental results were compared with the measurement, it can be seen that the online calculated and the experimental measuring results are in good agreement.

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Section: Methodsmentioning

confidence: 99%

Experimental Testing of the Radiation Shielding Properties for Steel

WAHEED¹

2022

International Journal of Computational and Experimental Science and Engineering

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“…1 Map of area of the investigation Fig. 2 Picture Showing Na(TI) Gamma Ray Spectrometer [33] where C r is the radionuclide activity concentration in the standard reference sample, M r is the mass of standard reference sample, I r is the peak intensity of the radionuclide in the standard sample, C s is the activity of radionuclide in the sample, M s is the mass of the sample and I s is the peak intensity of the radionuclide in the sample.…”

Section: Radioactivity Concentrationmentioning

confidence: 99%

Investigation into radioactivity levels in soil samples from wheat cultivation sites in Kapchorwa district Uganda

Sead,

Uzorka,

Olaniyan

2024

Discov Environ

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Using a NaI(Tl) gamma ray spectrometer, the activity concentrations of three natural radionuclides, 238U, 232Th, and 40K, were assessed for soil samples taken from various locations within the Kapchorwa district wheat plantation region. The average values found for 238U, 232Th, and 40K are 47.8 ± 4.1 Bqkg−1, 61.0 ± 3.8 Bqkg−1, and 1339.05 ± 65.3 Bqkg−1, respectively, all of which were above world average values. Radiological health hazard indices were calculated, including radium equivalent activity, absorbed dose rate, annual effective dose equivalent, external and internal health hazard indices, as well as gamma and alpha indices. The findings revealed that the annual effective dose equivalent (HR) and absorbed dose rate (DR) are respectively 0.58 ± 0.03 mSvy−1 and 118.1 ± 7.7 nGyh−1, and the mean value of radium equivalent activity is 246.9 ± 10.4 Bqkg−1. The gamma and alpha health hazard indices have values of 0.93 ± 0.05 and 0.25 ± 0.02, respectively, whereas the external and internal health hazard indices have values of 0.66 ± 0.04 and 0.79 ± 0.04, respectively. The findings showed that although the soil's radioactivity levels were higher than acceptable limits established by international standards, the computed hazard indices were lower than acceptable limits established by international standards, indicating a low risk of radiation contamination in the region. Important information about the natural radioactivity levels in agricultural soils and their effects on the environment and public health in Kapchorwa District and surrounding areas is provided by this study.

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“…Also, the current simulation provides a deep understanding of the interactions that occur in a real physical practical system. As can be done by experimental 5,6 or theoretical 7,8 approaches, Monte Carlo technique has been used in gamma detection techniques which have a fundamental role in the field of gamma-rays spectroscopy 9,10 applied in nuclear physics, radiation measurement of environmental samples radiation dosimetry [11][12][13][14][15] , medical radiography 16 , neutron activation analysis 17 , well logging 18 , and study of cosmic rays 19 .…”

Section: Introductionmentioning

confidence: 99%

Radioactive Source-Detector System: Design and Monte Carlo Opinion

Ali,

Mohammed

2024

Baghdad Sci.J

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تم في البحث الحالي تصميم و كتابة برنامج محاكاة حاسوبي وفقاً لطريقة مونت كارلو ليكون بمثابة نظام عملي إفتراضي بديلاً عن النظام الحقيقي. تم إختبار البرنامج إحصائياً و هندسياً وعددياً لنظام إفتراضي لمصدر مشع- كاشف. تم تنفيذ البرنامج لكاشف آيوديد الصوديوم ولعداد كايكر لمدى من الطاقة يصل إلى 10 MeV. تم استخدام قانون الأعداد الكبيرة (LLN) ونظرية النهاية المركزية (CLT) لاختبار دقة وضبط سير عمل البرنامج والإشارة إلى مدى قرب النتائج من متوسطاتها، وإحصائيًا، إلى أي مدى تميل إلى التوزيع الطبيعي. بشكل عام، أظهرت نتائج عدد من أنواع كفاءة الكاشف توافقاً كبيراً مع النتائج التجريبية المنشورة ونتائج عدد من البرامج العالمية ضمن نسبة خطأ 0,02-5% (أي دقة 95-99,98%) و بمستوى دلالة إحصائية يعكس إحكام خوارزمية المحاكاة. إن التخمين الدقيق والمضبوط للمحاكاة الحالية يمنحها الموثوقية المطلوبة. كما أظهر برنامج المحاكاة الحالي مرونة و فعالية عالية في تصميم أي نظام مصدر- كاشف نووي و تزويد العاملين أو المجربين ذات العلاقة بمؤشرات تساعد في التصميم الأمثل للمنظومة من حيث المكونات و هندسية النظام بأقل مدة زمنية. والتي قد تستغرق من بضعة ثواني الى بضعة دقائق لزمن تنفيذ بإستخدام حاسوب شخصي بمواصفات عادية. على عكس التجارب المختبرية التي قد تستغرق من عدة دقائق الى عدة ساعات. إضافة الى توفير بيئة عمل مثالية خالية من الإشعاع تماما". كما يقدم البرنامج الحالي فهماً عميقاً لما يحدث من تفاعلات في النظام الفيزيائي العملي الحقيقي.

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Performance of NaI(Tl) detector for gamma-ray spectroscopy

Cited by 13 publications

References 25 publications

Experimental Testing of the Radiation Shielding Properties for Steel

Experimental Testing of the Radiation Shielding Properties for Steel

Investigation into radioactivity levels in soil samples from wheat cultivation sites in Kapchorwa district Uganda

Radioactive Source-Detector System: Design and Monte Carlo Opinion

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