Evaluation of Monte Carlo-based calibrations of HPGe detectors for in situ gamma-ray spectrometry

2009 ◽  
Vol 100 (11) ◽  
pp. 935-940 ◽  
Author(s):  
Jonas Boson ◽  
Agneta H. Plamboeck ◽  
Henrik Ramebäck ◽  
Göran Ågren ◽  
Lennart Johansson
Keyword(s):  
Monte Carlo ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Hpge Detectors

scholarly journals Measurement of anthropogenic radionuclides in post-Fukushima Pacific seawater samples

Nukleonika ◽  
2015 ◽  
Vol 60 (3) ◽  
pp. 545-550 ◽  
Author(s):  
Guillaume Lutter ◽  
Faidra Tzika ◽  
Mikael Hult ◽  
Michio Aoyama ◽  
Yasunori Hamajima ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Power Plant ◽  
North Pacific ◽  
Nuclear Power ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Anthropogenic Radionuclides ◽  
Vast Number ◽  
Hpge Detectors ◽  
Seawater Samples

Abstract Following the accident at the Daiichi Fukushima nuclear power plant in 2011, a vast number of Pacific seawater samples from many locations far from Fukushima have been collected by Japanese investigators. Due to dilution, the activities of radionuclides from North Pacific seawater samples are very low, which calls for extraordinary measures when being measured. This study focuses on the metrological aspects of the gamma-ray spectrometry measurements performed on such samples in two underground laboratories; at HADES (by JRC-IRMM in Belgium), and at Ogoya (by Kanazawa University in Japan). Due to many samples and long measurement times, all available HPGe detectors needed to be employed. In addition to single coaxial detectors, this involved multidetector systems and well detectors. Optimization of detection limits for different radionuclides and detectors was performed using Monte Carlo simulations.

scholarly journals Application of a new in situ calibration technique for gamma spectrometry and comparison of in situ and laboratory measurements

2021 ◽  
Vol 72 (1) ◽  
pp. 29-35
Author(s):  
Davor Rašeta ◽  
Branko Petrinec ◽  
Dinko Babić ◽  
Marko Šoštarić
Keyword(s):  
Gamma Spectrometry ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Nuclear Accidents ◽  
Laboratory Measurements ◽  
Calibration Technique ◽  
In Situ Calibration ◽  
Hpge Detectors ◽  
Complicated Process

Abstract In situ gamma ray spectrometry was developed to quickly measure large areas of land following nuclear accidents. However, a proper calibration of detectors for in situ measurements is a long and complicated process. One tool designed to make this calibration quick is the InSiCal software. We compared 5,000 s in situ measurements with two different HPGe detectors calibrated using the InSiCal software and laboratory measurements of samples collected at the same locations. Our findings suggest that in situ gamma spectrometry using InSiCal software can provide reasonably accurate data, but some improvements are needed.

Application of the Monte Carlo code DETEFF to efficiency calibrations for in situ gamma-ray spectrometry

2012 ◽  
Vol 70 (5) ◽  
pp. 868-871 ◽  
Author(s):  
J. Carrazana González ◽  
N. Cornejo Díaz ◽  
M. Jurado Vargas
Keyword(s):  
Monte Carlo ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Monte Carlo Code

scholarly journals Progress in radionuclide characterisation in marine sediments using an underwater gamma-ray spectrometer in 2π geometry

2019 ◽  
Vol 21 ◽  
pp. 29
Author(s):  
E. G. Androulakaki ◽  
C. Tsabaris ◽  
M. Kokkoris ◽  
G. Eleftheriou ◽  
D. L. Patiris ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Detection System ◽  
Full Energy Peak ◽  
Gamma Ray Spectrometry ◽  
Peak Efficiency ◽  
Full Energy ◽  
Effective Manner ◽  
Energy Peak ◽  
Full Energy Peak Efficiency

The in-situ gamma-ray spectrometry is a well suited method for seabed mapping applications, since it provides rapid results in a cost effective manner. Moreover, the in-situ method is preferable to the commonly applied laboratory measurements, due to its beneficial characteristics. Therefore, the development of in-situ systems for seabed measurements continuously grows. However, an efficiency calibration of the detection system is necessary for obtaining quantitative results in the full spectral range. In the present work, an approach for calculating the full-energy peak efficiency of an underwater insitu spectrometer for measure- ments on the seabed is presented. The experimental work was performed at the coastal site of Vasilikos (Cyprus). The experimental full-energy peak efficiency of the in-situ was determined in the energy range 1400–2600 keV, by combining the in-situ and laboratory reference measurements. The experimental effi- ciency results were theoretically reproduced by means of Monte Carlo (MC) simulations, using the MCNP5 code.

scholarly journals Experimental and Simulated Spectral Gamma-Ray Response of a NaI(Tl) Scintillation Detector used in Airborne Gamma-Ray Spectrometry

2021 ◽  
Author(s):  
David Breitenmoser
Keyword(s):  
Monte Carlo ◽  
Gamma Ray ◽  
Radiation Transport ◽  
Natural Uranium ◽  
Detector Response ◽  
Gamma Ray Spectrometry ◽  
Response Analysis ◽  
Maximum Relative Error ◽  
Potassium Sources ◽  
Significant Difference

<p>The objective of this work is to simulate the spectral gamma-ray response of NaI(Tl) scintillation detectors for airborne gamma-ray spectrometry (AGRS) using Monte Carlo radiation transport codes. The study is based on a commercial airborne gamma-ray spectrometry detector system with four individual NaI(Tl) scintillation crystals and a total volume of 16.8 l. Monte Carlo source-detector simulations were performed in an event-by-event mode with the commercial multi-purpose transport codes MCNP6.2 and FLUKA. Validation measurements were conducted using <sup>241</sup>Am, <sup>133</sup>Ba, <sup>60</sup>Co, <sup>137</sup>Cs and <sup>152</sup>Eu radiation sources with known activities and source-detector geometries. Energy resolution functions were derived from these measurements combined with additional measurements of natural Uranium, Thorium and Potassium sources. The simulation results are in good agreement with the experimental data with a maximum relative error in the full-energy peak counts of 10%. In addition, no significant difference between the two Monte Carlo radiation transport codes was found with respect to a 95% confidence level. The validated detector model presented herein can be adopted for angular detector response analysis and calibration computations relating radionuclide activity concentrations with spectral detector counts.</p>

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