Determination of the neutron and gamma ray dose rates of the irradiating beam tubes of a pool-type research reactor by using Monte Carlo simulation and experimental detectors regarding radiation protection issues

The epitaxially grown (GaAs)Ge thin film has been arousing much interest because it is one of metastable alloys of III-V compound semiconductors with germanium and a possible candidate in optoelectronic applications. It is important to be able to accurately determine the composition of the film, particularly whether or not the GaAs component is in stoichiometry, but x-ray energy dispersive analysis (EDS) cannot meet this need. The thickness of the film is usually about 0.5-1.5 μm. If Kα peaks are used for quantification, the accelerating voltage must be more than 10 kV in order for these peaks to be excited. Under this voltage, the generation depth of x-ray photons approaches 1 μm, as evidenced by a Monte Carlo simulation and actual x-ray intensity measurement as discussed below. If a lower voltage is used to reduce the generation depth, their L peaks have to be used. But these L peaks actually are merged as one big hump simply because the atomic numbers of these three elements are relatively small and close together, and the EDS energy resolution is limited.

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Monte Carlo Simulation of the Gamma-Ray Transmissions for the newly Designed Shielding Blocks used in Radiotherapy

Çanakkale Onsekiz Mart Üniversitesi Fen Bilimleri Enstitüsü Dergisi ◽

10.28979/comufbed.753299 ◽

2020 ◽

Author(s):

Nuray YAVUZKANAT ◽

Hazal Burcu SARAÇ KÜREM

Keyword(s):

Monte Carlo Simulation ◽

Monte Carlo ◽

Gamma Ray

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Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

Radiochimica Acta ◽

10.1515/ract-2020-0067 ◽

2020 ◽

Vol 0 (0) ◽

Author(s):

Bünyamin Aygün ◽

Erdem Şakar ◽

Abdulhalik Karabulut ◽

Bünyamin Alım ◽

Mohammed I. Sayyed ◽

...

Keyword(s):

Monte Carlo Simulation ◽

Monte Carlo ◽

Fast Neutron ◽

Cross Sections ◽

Gamma Ray ◽

Absorbed Dose ◽

Neutron Shielding ◽

Shielding Properties ◽

Effective Neutron ◽

Simulation Codes

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

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