The Simulation of Low-Background Gamma Spectrometer With Clover Detector

2013 ◽  
Author(s):  
Huilan Liu ◽  
Yushou Song ◽  
Zhaoyang Xie ◽  
Baodong Sun
Keyword(s):  
Nuclear Physics ◽  
High Performance ◽  
Gamma Ray ◽  
Germanium Detector ◽  
Gamma Detector ◽  
Gamma Spectrometer ◽  
Radiation Level ◽  
Low Background ◽  
Clover Detector ◽  
Main Detector

A low-background gamma spectrometer consists of a high-performance gamma detector and a low-background chamber. It is widely used to monitor the radiation level of the environment and to identify the species of the radiological source. It is especially important for the analysis of the nuclear accident. Usually a high purity Germanium detector (HPGe) is used as a gamma ray detector. In order to enhance the detecting accuracy and sensitivity, it is essential to improve the performance of the gamma detector. In recent years, a clover detector composed of four coaxial HPGe crystals appear and is widely utilized in nuclear physics experimental research. Because of the larger dimensions and segmented structure, it displays outstanding characteristics different from traditional HPGe detectors. With a clover detector as the main detector and the HPLBS1 chamber of ORTEC as the lead chamber, the low-background gamma spectrometer is simulated by the Monte Carlo toolkit GEANT4, where the interaction processes of gamma ray provided by the GEANT4 physics list is used. The detecting performance of the low-background gamma spectrometer such as detecting efficiency and peak-total ratio are given. The results indicate that low-background gamma spectrometer with a clover as the main detector has better characteristic than that with HPGe as a main detector traditionally.

scholarly journals Low-background, digital gamma-ray spectrometer with BEGe detector and active shield: commissioning, optimisation and software development

2019 ◽  
Vol 322 (3) ◽  
pp. 1311-1321
Author(s):  
Krzysztof Gorzkiewicz ◽  
Jerzy Wojciech Mietelski ◽  
Renata Kierepko ◽  
Kamil Brudecki
Keyword(s):  
Gamma Ray ◽  
Germanium Detector ◽  
Low Background ◽  
Gamma Ray Spectrometer ◽  
Annihilation Peak ◽  
The Mean ◽  
Plastic Scintillators ◽  
Set Up ◽  
Active Shield ◽  
Broad Energy

Abstract This paper presents results of the development process of low-background, digital gamma-rays spectrometer equipped with Broad Energy Germanium detector (CANBERRA BE5030), multi-layer passive shield and cosmic veto system that consists of five plastic scintillators (SCIONIX EJ-200). Data acquisition is performed using digitizer CAEN DT5725 with CoMPASS software. Output data analysis is carried out with purposely written and developed code VETO. On the basis of conducted tests, acquisition parameters were set up and tuned as well as time delays between all detectors were established. As a result of the configuration process, the mean background counts reduction of 64% in the whole spectrum and 65% in annihilation peak were achieved. This procedure allowed diminishing detection limits of selected isotopes 37% on average.

scholarly journals Assessing an accuracy of vgspec program through ability of calculating peak area, automatically finding the peak, identifying isotopes and determining radioactivity for cylindrical and marinelli sources

2013 ◽  
Vol 16 (3) ◽  
pp. 83-92
Author(s):  
Vinh Quang Trinh ◽  
Loan Thi Hong Truong ◽  
Nhon Van Mai
Keyword(s):  
Nuclear Physics ◽  
Hpge Detector ◽  
Gamma Spectrum ◽  
Experimental Results ◽  
Radioactive Isotopes ◽  
Gamma Spectrometer ◽  
Low Background ◽  
Processing Program ◽  
Physics Department

Genie 2000 version of gamma spectrum processing program, which is being used at Nuclear Physics Department, Physics – Technique Physics Faculty, University of Science is lacked of package for determining radioactivity of sources, also has not been comprehensibly automatic from analysis and process to identification of radioactive isotopes and evaluation of source activity. We have built version 2.1 of VGSpec program to determine source radioactivity. Then, the experiments are carried out to measure cylindrical standard and Marinelli samples by low background gamma spectrometer using HPGe detector, to compare experimental results with ones of the program, as well as assess the accuracy of VGSpec program through ability of determining radioactivity for cylindrical and Marinelli sources.

scholarly journals A Low Background Gamma Ray Spectrometer with Anticosmic Shielding

2016 ◽  
Vol 26 (1) ◽  
pp. 93
Author(s):  
Nguyen Quoc Hung ◽  
Vo Hong Hai ◽  
Tran Kim Tuyet ◽  
Ho Lai Tuan
Keyword(s):  
Nuclear Physics ◽  
Gamma Ray ◽  
Gamma Line ◽  
Background Suppression ◽  
Background Count ◽  
Background Count Rate ◽  
Low Background ◽  
Lead Shield ◽  
Gamma Ray Spectrometer ◽  
National University

The article describes a gamma ray spectrometer protected by a lead shield (Model 747E Canberra lead shield) and an active shield made of an 80~cm \(\times\) 80~cm \(\times\) 3~cm plastic scintillator plate in anticoincidence on top of the lead shield. The detector used as low background gamma-spectrometer is a high purity Germanium crystal of model GC2018 Canberra. The background count rate currently achieved (30-2400 keV) is 1.27 cps without anticoincidence. The level of background suppression obtained from the active protection is 0.80 overall and about 0.43 for the 511 keV gamma line. The gamma ray spectrometer is installed and operated in the Nuclear Laboratory, Department of Nuclear Physics, University of Science, HCMC-Vietnam National University.

scholarly journals Validation of EFFTRAN for efficiency transfer to distant geometries and volume sources

2021 ◽  
Author(s):  
H. Ramebäck ◽  
S. Jonsson ◽  
T. Vidmar
Keyword(s):  
Methyl Methacrylate ◽  
Gamma Ray ◽  
Germanium Detector ◽  
Gamma Ray Spectrometry ◽  
Volume Source ◽  
Two Stage ◽  
Poly Methyl Methacrylate ◽  
Fit For Purpose

AbstractThe efficiency transfer procedure from a geometry where a volume source was placed directly on the endcap of a germanium detector to three different distant geometries was carried out using the EFFTRAN code. One of these distant geometries included absorbers consisting of poly(methyl methacrylate). The efficiency transfer to this geometry therefore had to be realized as a two-stage transfer, since a direct efficiency transfer is not possible using EFFTRAN in such a case. Efficiency transfer to all three distant geometries yielded results which can be considered as fit-for-purpose in e.g. most of the applications of gamma ray spectrometry.

GAMMA-RAY SPECTROSCOPY AT GANIL

2006 ◽  
Vol 15 (08) ◽  
pp. 1957-1965
Author(s):  
G. DE FRANCE
Keyword(s):  
Reaction Mechanism ◽  
Nuclear Structure ◽  
Nuclear Physics ◽  
Gamma Ray ◽  
Gamma Ray Spectroscopy ◽  
Comprehensive Picture ◽  
Clear Identification

Gamma-ray spectroscopy associated to the clear identification of the emitting nuclei is a key to understand in a coherent way the nuclear structure of the elements located far from stability. The coupling of very efficient gamma-ray arrays and spectrometers has pushed away the limits and opened up new possibilities in nuclear physics studies. These combinations give access to a comprehensive picture of both the reaction mechanism and the nuclear structure of a given nucleus. In this talk, the various possibilities offered at GANIL with such a coupling will be given.

Design, calibration, and application of an airborne gamma spectrometer system in Switzerland

Geophysics ◽  
1997 ◽  
Vol 62 (5) ◽  
pp. 1369-1378 ◽  
Author(s):  
Georg F. Schwarz ◽  
Ladislaus Rybach ◽  
Emile E. Klingelé
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Gamma Ray ◽  
Point Sources ◽  
Swiss Alps ◽  
Artificial Radioactivity ◽  
Radiation Level ◽  
Satellite Navigation System ◽  
Emergency Situations

Airborne radiometric surveys are finding increasingly wider applications in environmental mapping and monitoring. They are the most efficient tool to delimit surface contamination and to locate lost radioactive sources. To secure radiometric capability in survey and emergency situations, a new sensitive airborne system has been built that includes an airborne spectrometer with 256 channels and a sodium iodide detector with a total volume of 16.8 liters. A rack mounted PC with memory cards is used for data acquisition, with a GPS satellite navigation system for positioning. The system was calibrated with point sources using a mathematical correction to take into account the effects of gamma‐ray scattering in the ground and in the atmosphere. The calibration was complemented by high precision ground gamma spectrometry and laboratory measurements on rock samples. In Switzerland, two major research programs make use of the capabilities of airborne radiometric measurements. The first one concerns nuclear power plant monitoring. The five Swiss nuclear installations (four power plants and one research facility) and the surrounding regions of each site are surveyed annually. The project goal is to monitor the dose‐rate distribution and to provide a documented baseline database. The measurements show that all sites (with the exception of the Gösgen power plant) can be identified clearly on the maps. No artificial radioactivity that could not be explained by the Chernobyl release or earlier nuclear weapons tests was detected outside of the fenced sites of the nuclear installations. The second program aims at a better evaluation of the natural radiation level in Switzerland. The survey focused on the crystalline rocks of the Central Massifs of the Swiss Alps because of their relatively high natural radioactivity and lithological variability.

scholarly journals Using Gamma Spectroscopy to Calculate Radioactive Contaminants in Foreign and Local Tobacco Samples

2020 ◽  
Vol 55 (2) ◽  
Author(s):  
Ahmed F. Mkhaiber ◽  
Auday T. Al-Bayati ◽  
Enas A. Jawad ◽  
Khalid H. Mahdi
Keyword(s):  
Gamma Ray ◽  
Specific Activity ◽  
Gamma Spectroscopy ◽  
Natural Radionuclide ◽  
Germanium Detector ◽  
Average Concentration ◽  
Radium Equivalent Activity ◽  
Lifetime Cancer Risk ◽  
Potassium 40 ◽  
Thorium 232

The normal radioactivity levels of Uranium-238, Thorium-232, and Potassium-40 were calculated for ten types of foreign and local cigarettes available on the Iraqi market using a gamma-ray spectroscopy technique employing the germanium detector system. The results of this study showed that the average specific activity for each of Uranium-238, Thorium-232 and Potassium-40 were 21.689± 4.596, 18.906 ± 4.148, and 430.094 ± 19.449 (Bq/Kg) respectively. The annual effective dose, radium equivalent activity and excess lifetime cancer risk for the studied samples were also calculated, and their rates were 11.582 μsv/y, 81.841 Bq/Kg, and 40.538 people per million per year respectively. The outcomes indicate that the rate of concentration of uranium and thorium is lower than the permissible values, whereas the average concentration of potassium was slightly higher than the permissible values. This research is important because it warns against several types of cigarettes that contain high concentrations of radionuclides, which can lead to infection cancer and then lead to the death of the person who has used it profusely. Therefore, the aim of the current research is to evaluate the radiological risks of radionuclides in tobacco cigarette smoke by evaluating their natural radionuclide concentrations.

A low-background gamma spectrometer

1973 ◽  
Vol 34 (2) ◽  
pp. 162-164
Author(s):  
Yu. A. Surkov ◽  
O. P. Sobornov
Keyword(s):  
Gamma Spectrometer ◽  
Low Background
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