A Monte Carlo study of an energy-weighted algorithm for radionuclide analysis with a plastic scintillation detector

Shin, Wook; Lee, Hyun Cheol; Choi, Chang Il; Park, Chang Soo; Kim, Hong Suk; Min, Chul Hee

doi:10.1016/j.apradiso.2015.03.014

Cited by 16 publications

(10 citation statements)

References 12 publications

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“…In case of 137 Cs having a Compton edge at 0.477 MeV theoretically, it was already observed that the peak of the energyweighted spectrum that originated from the Compton maximum was a feature for nuclide identification in previous studies. Similarly, 60 Co having a clear Compton maximum of the energy spectrum at 1.041 MeV also exhibited a discernable peak in the energy-weighted spectrum [8][9][10][11]. Figs.…”

Section: Spectrum Analysis Of Moving Sourcesmentioning

confidence: 75%

“…2. The energy spectrum of 212 Bi as raw data was calculated using the Geant4 simulation under the same conditions as in the previous study [8]. It was observed that the peak obtained using the equation was more emphasized as the exponent of the "count" was raised to power as depicted in Fig.…”

Section: Jrpr (2)mentioning

confidence: 87%

“…The energy-weighted algorithm proposed in the previous studies multiplies the counts in each energy bin and the energy corresponding to the same channel (in the form of a coefficient) using the following equation: (1) where is the energy-weighted count of the energy spectrum's i th bin, is the original optical photon count in the i th bin, and is the energy coefficient in the i th bin [8][9][10][11]. Applying the equation, it was observed that the increased area, such as the Compton maximum of the gamma energy spectrum measured by the plastic scintillator, was converted into an identifiable peak as shown in Fig.…”

Section: Improvement Of Energy-weighted Algorithmmentioning

confidence: 99%

“…The Pacific Northwest National Laboratory (PNNL) has reported that several gamma sources such as 137 Cs or 60 Co have demonstrated an intrinsic Compton maximum in their energy spectrum [7]. Based on the physical properties of plastic scintillators, we had earlier proposed an energy-weighting algorithm that emphasizes the Compton maximum in the form of a peak by multiplying the counts per channel of the energy spectrum with the energy of the corresponding channel [8][9][10][11]. Using this algorithm, we could distinguish among 137 Cs, 60 Co, 226 Ra, and 22 Na in a lab-scale experiment.…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of Source Identification Method Based on Energy-Weighting Level with Portal Monitoring System Using Plastic Scintillator

et al. 2020

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Background: Radiation portal monitors (RPMs) involving plastic scintillators installed at the border inspection sites can detect illicit trafficking of radioactive sources in cargo containers within seconds. However, RPMs may generate false alarms because of the naturally occurring radioactive materials. To manage these false alarms, we previously suggested an energy-weighted algorithm that emphasizes the Compton-edge area as an outstanding peak. This study intends to evaluate the identification of radioactive sources using an improved energy-weighted algorithm. Materials and Methods: The algorithm was modified by increasing the energy weighting factor, and different peak combinations of the energy-weighted spectra were tested for source identification. A commercialized RPM system was used to measure the energy-weighted spectra. The RPM comprised two large plastic scintillators with dimensions of 174 × 29 × 7 cm 3 facing each other at a distance of 4.6 m. In addition, the in-house-fabricated signal processing boards were connected to collect the signal converted into a spectrum. Further, the spectra from eight radioactive sources, including special nuclear materials (SNMs), which were set in motion using a linear motion system (LMS) and a cargo truck, were estimated to identify the source identification rate. Results and Discussion: Each energy-weighted spectrum exhibited a specific peak location, although high statistical fluctuation errors could be observed in the spectrum with the increasing source speed. In particular, 137 Cs and 60 Co in motion were identified completely (100%) at speeds of 5 and 10 km/hr. Further, SNMs, which trigger the RPM alarm, were identified approximately 80% of the time at both the aforementioned speeds. Conclusion: Using the modified energy-weighted algorithm, several characteristics of the energy weighted spectra could be observed when the used sources were in motion and when the geometric efficiency was low. In particular, the discrimination between 60 Co and 40 K, which triggers false alarms at the primary inspection sites, can be improved using the proposed algorithm.

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Section: Spectrum Analysis Of Moving Sourcesmentioning

confidence: 75%

Section: Jrpr (2)mentioning

confidence: 87%

Section: Improvement Of Energy-weighted Algorithmmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Evaluation of Source Identification Method Based on Energy-Weighting Level with Portal Monitoring System Using Plastic Scintillator

et al. 2020

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“…Therefore, various spectral processing techniques have been reported for pseudo gamma spectroscopy of plastic scintillation detectors. Energy windowing [1][2][3][4], F-score analysis [5], energy weighted algorithms [6,7], and inverse matrix [8] are representative methods for pseudo gamma spectroscopy. However, these methods can be categorized as indirect pseudo gamma spectroscopic methods because it is impossible to directly identify the energy of incident gamma rays.…”

Section: Introductionmentioning

confidence: 99%

Reconstruction of Compton Edges in Plastic Gamma Spectra Using Deep Autoencoder

Jeon

Lee

Moon

et al. 2020

Sensors

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Plastic scintillation detectors are widely utilized in radiation measurement because of their unique characteristics. However, they are generally used for counting applications because of the energy broadening effect and the absence of a photo peak in their spectra. To overcome their weaknesses, many studies on pseudo spectroscopy have been reported, but most of them have not been able to directly identify the energy of incident gamma rays. In this paper, we propose a method to reconstruct Compton edges in plastic gamma spectra using an artificial neural network for direct pseudo gamma spectroscopy. Spectra simulated using MCNP 6.2 software were used to generate training and validation sets. Our model was trained to reconstruct Compton edges in plastic gamma spectra. In addition, we aimed for our model to be capable of reconstructing Compton edges even for spectra having poor counting statistics by designing a dataset generation procedure. Minimum reconstructible counts for single isotopes were evaluated with metric of mean averaged percentage error as 650 for 60Co, 2000 for 137Cs, 3050 for 22Na, and 3750 for 133Ba. The performance of our model was verified using the simulated spectra measured by a PVT detector. Although our model was trained using simulation data only, it successfully reconstructed Compton edges even in measured gamma spectra with poor counting statistics.

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Fabrication of a Liquid Scintillator based on 7-Diethylamino-4-Methylcoumarin for Radiation Detection

et al. 2023

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Organic scintillation detectors are widely used to measure the presence or absence of radiation. With these devices, there are advantages in that they are easy to manufacture, large in size, and have a short uorescence decay time. However, they are not suitable for gamma measurements because they are composed of a low-atomic-number material. In this regard, alternative materials for the secondary solute used in basic organic scintillators have been investigated, and the applicability of alternative materials, the detection characteristics, and neutron/gamma identi cation tests were all assessed. 7-Diethylamino-4-methylcoumarin (DMC), selected as an alternative material, is a benzopyrone derivative in the form of colorless crystals with high uorescence, a high quantum yield in the visible region, and excellent light stability. In addition, it has a large Stokes shift, and solubility in a solvent is good. Through an analysis in this study, it was found that the absorption wavelength range of DMC coincides with the emission wavelength range of PPO, which is the primary solute used with DMC. Finally, it was con rmed that the optimal concentration of DMC was 0.08 wt%. As a result of performing gamma and neutron measurement tests using a DMC-based liquid scintillator, it was found to perform well (FOM = 1.42) compared to a commercial liquid scintillator, BC501A.

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A Monte Carlo study of an energy-weighted algorithm for radionuclide analysis with a plastic scintillation detector

Cited by 16 publications

References 12 publications

Evaluation of Source Identification Method Based on Energy-Weighting Level with Portal Monitoring System Using Plastic Scintillator

Evaluation of Source Identification Method Based on Energy-Weighting Level with Portal Monitoring System Using Plastic Scintillator

Reconstruction of Compton Edges in Plastic Gamma Spectra Using Deep Autoencoder

Fabrication of a Liquid Scintillator based on 7-Diethylamino-4-Methylcoumarin for Radiation Detection

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