• Title/Summary/Keyword: $\gamma$-measurements

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Development of a Portable Detection System for Simultaneous Measurements of Neutrons and Gamma Rays (중성자선과 감마선 동시측정이 가능한 휴대용 계측시스템 개발에 관한 연구)

  • Kim, Hui-Gyeong;Hong, Yong-Ho;Jung, Young-Seok;Kim, Jae-Hyun;Park, Sooyeun
    • Journal of radiological science and technology
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    • v.43 no.6
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    • pp.481-487
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    • 2020
  • Radiation measurement technology has steadily improved and its usage is expanding in various industries such as nuclear medicine, security search, satellite, nondestructive testing, environmental industries and the domain of nuclear power plants (NPPs). Especially, the simultaneous measurements of gamma rays and neutrons can be even more critical for nuclear safety management of spent nuclear fuel and monitoring of the nuclear material. A semiconductor detector comprising cadmium, zinc, and tellurium (CZT) enables to detect gamma-rays due to the significant atomic weight of the elements via immediate neutron and gamma-ray detection. Semiconductor sensors might be used for nuclear safety management by monitoring nuclear materials and spent nuclear fuel with high spatial resolution as well as providing real-time measurements. We aim to introduce a portable nuclide-analysis device that enables the simultaneous measurements of neutrons and gamma rays using a CZT sensor. The detector has a high density and wide energy band gap, and thus exhibits highly sensitive physical characteristics and characteristics are required for performing neutron and gamma-ray detection. Portable nuclide-analysis device is used on NPP-decommissioning sites or the purpose of nuclear nonproliferation, it will rapidly detect the nuclear material and provide radioactive-material information. Eventually, portable nuclide-analysis device can reduce measurement time and economic costs by providing a basis for rational decision making.

Gamma Evaluation with Portal Dosimetry for Volumetric Modulated Arc Therapy and Intensity-Modulated Radiation Therapy

  • Kim, Jung-in;Choi, Chang Heon;Park, So-Yeon;An, HyunJoon;Wu, Hong-Gyun;Park, Jong Min
    • Progress in Medical Physics
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    • v.28 no.2
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    • pp.61-66
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    • 2017
  • The aim of this study is to investigate the characteristics of portal dosimetry in comparison with the MapCHECK2 measurments. In this study, a total of 65 treatment plans including both volumetric modulated arc therapy (VMAT) and intensity-modulated radiation therapy (IMRT) were retrospectively selected and analyzed (45 VMAT plans and 20 IMRT plans). A total of 4 types of linac models (VitalBeam, Trilogy, Clinac 21EXS, and Clianc iX) were used for the comparison between portal dosimetry and the MapCHECK2 measurements. The VMAT plans were delivered with two VitalBeam linacs (VitalBeam1 and VitalBeam2) and one Trilogy while the IMRT plans were delivered with one Clinac 21EXS and one Clinacl iX. The global gamma passing rates of portal dosimetry and the MapCHECK2 measurements were analyzed with a gamma criterion of 3%/3 mm for IMRT while those were analyzed with a gamma criterion of 2%/2 mm for VMAT. Spearman's correlation coefficients (r) were calculated between the gamma passing rates of portal dosimetry and those of the MapCHECK2 measurements. For VMAT, the gamma passing rates of portal dosimetry with the VitalBeam1, VitalBeam2, and Trilogy were $97.3%{\pm}3.5%$, $97.1%{\pm}3.4%$, and $97.5%{\pm}1.9%$, respectively. Those of the MapCHECK2 measurements were $96.8%{\pm}2.5%$, $96.3%{\pm}2.7%$, and $97.4%{\pm}1.3%$, respectively. For IMRT, the gamma passing rates of portal dosimetry with Clinac 21EXS and Clinac iX were $99.7%{\pm}0.3%$ and $99.8%{\pm}0.2%$, respectively. Those of the MapCHECK2 measurements were $96.5%{\pm}3.3%$ and $97.7%{\pm}3.2%$, respectively. Except for the result with the Trilogy, no correlations were observed between the gamma passing rates of portal dosimetry and those of the MapCHECK2 measurements. Therefore, both the MapCHECK2 measurements and portal dosimetry can be used as an alternative to each other for patient-specific QA for both IMRT and VMAT.

Using machine learning for anomaly detection on a system-on-chip under gamma radiation

  • Eduardo Weber Wachter ;Server Kasap ;Sefki Kolozali ;Xiaojun Zhai ;Shoaib Ehsan;Klaus D. McDonald-Maier
    • Nuclear Engineering and Technology
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    • v.54 no.11
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    • pp.3985-3995
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    • 2022
  • The emergence of new nanoscale technologies has imposed significant challenges to designing reliable electronic systems in radiation environments. A few types of radiation like Total Ionizing Dose (TID) can cause permanent damages on such nanoscale electronic devices, and current state-of-the-art technologies to tackle TID make use of expensive radiation-hardened devices. This paper focuses on a novel and different approach: using machine learning algorithms on consumer electronic level Field Programmable Gate Arrays (FPGAs) to tackle TID effects and monitor them to replace before they stop working. This condition has a research challenge to anticipate when the board results in a total failure due to TID effects. We observed internal measurements of FPGA boards under gamma radiation and used three different anomaly detection machine learning (ML) algorithms to detect anomalies in the sensor measurements in a gamma-radiated environment. The statistical results show a highly significant relationship between the gamma radiation exposure levels and the board measurements. Moreover, our anomaly detection results have shown that a One-Class SVM with Radial Basis Function Kernel has an average recall score of 0.95. Also, all anomalies can be detected before the boards are entirely inoperative, i.e. voltages drop to zero and confirmed with a sanity check.

Development of a DDA+PGA-combined non-destructive active interrogation system in "Active-N"

  • Kazuyoshi Furutaka;Akira Ohzu;Yosuke Toh
    • Nuclear Engineering and Technology
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    • v.55 no.11
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    • pp.4002-4018
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    • 2023
  • An integrated neutron interrogation system has been developed for non-destructive assay of highly-radioactive special nuclear materials, to accumulate knowledge of the method through developing and using it. The system combines a differential die-away (DDA) measurement system for the quantification of nuclear materials and a prompt gamma-ray analysis (PGA) system for the detection of neutron poisons which disturb the DDA measurements; a common D-T neutron generator is used. A special care has been taken for the selection of materials to reduce the background gamma rays produced by the interrogation neutrons. A series of measurements were performed to test the basic performance of the system. The results show that the DDA system can quantify plutonium of as small as 20 mg and it is not affected by intense neutron background up to 1.57 × 107 s-1 and gamma ray of 4.43 × 1010 s-1. The gamma-ray background counting rate at the PGA detector was reduced down to 3.9 × 103 s-1 even with the use of the D-T neutron generator. The test measurements show that the PGA system is capable of detecting 0.783 g of boron and about 86.8 g of gadolinium in 30 min.

Measurements of X-Ray and Gamma Ray Dosse Rate by the Silicon P-N Junction Diode (Silicon P-N Junction Diode에 대한 X-Ray 및 Gamma-Ray 의 Dose Ratec 측정)

  • 정만영;김덕진
    • 전기의세계
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    • v.13 no.3
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    • pp.13-20
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    • 1964
  • The measurements of X-ray and Gamma-ray Dose Rate have been successfully made by measuring the short circuit current of the Silicon P-N Junction Diode being irradiated. The short circuit current flows when a silicon P-N Junction Diode is irradiated by X-ray of Gammaray radiations due to photovoltaic effect. A brief analysis is given in order to verify the proportionality of a short circuit current to the Dose Rate. Using this method, measurements of X-ray Dose Rate were carried out in the range of 0.05-1600 r/m successfully. The calibration was made by comparing with Victoreen condenser r-meter. Some advantages in this Dose Rate meter over a condenser r-meter were found. One can measure a continous variation of X-ray Dose Rate with this rate meter at the control console of X-ray device.

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Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

  • Czakoj, Tomas;Kostal, Michal;Losa, Evzen;Matej, Zdenek;Simon, Jan;Mravec, Filip;Cvachovec, Frantisek
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3824-3832
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    • 2022
  • Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7-9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak.

Full spectrum estimation of helicopter background and cosmic gamma-ray contribution for airborne measurements

  • Lukas Kotik;Marcel Ohera
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.1052-1060
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    • 2023
  • The airborne radiation monitoring has been used in geophysics for more than forty years and now it also has its important role in emergency monitoring. The aircraft background and the cosmic gamma-rays contribute to the measured gamma spectrum on the aircraft board. This adverse effect should be eliminated before the data processing. The paper describes two semiparametric methods to estimate the full spectrum aircraft background and cosmic gamma-ray contribution from spectra measured at altitudes where terrestrial contribution is negligible. The methods only assume to know possible peak positions in spectra and their full width at half maximum, that can be easily obtained e.g. from terrestrial measurement. The methods were applied to real experimental data acquired on Mi-17 and Bell 412 helicopter boards. The IRIS airborne gamma-ray spectrometer, with 4×4 L NaI(Tl) crystals, produced by Pico Envirotec Inc., Canada, was used on helicopters' boards. To obtain valid estimate of the aircraft background and the cosmic contribution, the measurements over sea and large water areas were carried out. However, the satisfactory results over inland were also achieved comparing with those acquired over large water areas.

Comparison of Physical Properties obtained from Geophysical Well Log and Core Property Measurements in Gabsan Formation (갑산층 석회암지역에서의 코어물성과 검층물성 비교)

  • 김영화;김기주
    • The Journal of Engineering Geology
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    • v.9 no.3
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    • pp.253-265
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    • 1999
  • Physical properties of Paleozoic sedimentary rocks in Gabsan formation in Jechon area were obtained by both geophysical well log methods and core property measurements, and the similarity and difference shown between the well log and core log responses were analyzed. The physical properties obtained are natural gamma, resistivity and density. From the difference in density response between the well log and core measurement, the need of correction for natural gamma effect on density log was strongly suggested. And fairly good correlation was obtained between well log and core properties, and among natural gamma, resistivity and density by applying natural gamma correction on density log. It is noted that shale in Gabsan formation reveals very high density, even higher than the density of adjacent non-porous limestone.

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Measurements of the Direction and Polarization Correlation for Cascade Gamma-rays of Co-60 and Cs-134 (Co-60과 Cs-134의 연발감마선에 대한 방향 및 편극상관 측정)

  • Hyung-Ju Woo;Kie-Hyung Chung;Hae-Ill Bak
    • Nuclear Engineering and Technology
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    • v.14 no.2
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    • pp.64-69
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    • 1982
  • Directional correlation measurements for the Co-60 and Cs-134 cascade gamma-rays have been performed in the angular range from 90$^{\circ}$ to 180$^{\circ}$ by use of the fast coincidence scintillation spectrometer incorporated with a gamma-ray polarimeter based on the Compton scattering effect to determine the polarization correlations. The experimental method together with the theoretical background is described, and the results are shown graphically to represent the consistency of the measurement with approximate theoretical estimates.

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Detection of voluminous gamma-ray source with a collimation beam geometry and comparison with peak efficiency calculations of EXVol

  • Kang, M.Y.;Sun, G.M.;Choi, H.D.
    • Nuclear Engineering and Technology
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    • v.52 no.11
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    • pp.2601-2606
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    • 2020
  • In this study, we expanded the performance of the existing EXVol code and performed empirical experiments and calculations. A high-resolution gamma spectroscopy system was constructed, and a standard point source and a standard volume source were measured with an HPGe detector with 43.1% relative efficiency. EXVol was verified by quantitative comparison of the detection efficiencies determined by measurements and calculations. To introduce the concept of the detector scanning that occurs in the actual measurement into the EXVol code, a collimator was placed between the source and detector. The detection efficiency was determined in the asymmetric arrangement of the source and detector with a collimator. A collimator made of lead with a diameter of 15 mm and a thickness of 50 mm was installed between the source and the detector to determine the detection efficiency at a specific location. The calculation result was contour plotted so that the distribution of detection efficiency could be visually confirmed. The relative deviation between the measurements and calculations for the coaxial and asymmetric structures was 10%, and that for the collimation structure was 20%. The results of this study can be applied to research using γ-ray measurements.