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- 저자 : S. Farhad Masoudi (검색결과 3 건)
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Lost gamma source detection algorithm based on convolutional neural network
Fathi, Atefeh,Masoudi, S. Farhad Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.11
Based on the convolutional neural network (CNN), a novel technique is investigated for lost gamma source detection in a room. The CNN is trained with the result of a GEANT4 simulation containing a gamma source inside a meshed room. The dataset for the training process is the deposited energy in the meshes of different n-step paths. The neural network is optimized with parameters such as the number of input data and path length. Based on the proposed method, the place of the gamma source can be recognized with reasonable accuracy without human intervention. The results show that only by 5 measurements of the energy deposited in a 5-step path, (5 sequential points 50 cm apart within 1600 meshes), the gamma source location can be estimated with 94% accuracy. Also, the method is tested for the room geometry containing the interior walls. The results show 90% accuracy with the energy deposition measurement in the meshes of a 5-step path.
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Masoumi Mahnoush,Masoudi S. Farhad,Rahmani Faezeh 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.11
The optimized design of a Neutron Activation Analysis (NAA) system, including Delayed Gamma NAA (DGNAA) and Prompt Gamma NAA (PGNAA), has been proposed in this research based on Mevex Linac with 5 MeV electron energy and 50 kW power as a neutron source. Based on the MCNPX 2.6 simulation, the optimized configuration contains; tungsten as an electron-photon converter, BeO as a photoneutron target, BeD2 and plexiglass as moderators, and graphite as a reflector and collimator, as well as lead as a gamma shield. The obtained thermal neutron flux at the beam port is equal to 2.06× 109 (#/cm2.s). In addition, using the optimized neutron beam, the detection limit has been calculated for some elements such as H-1, B-10, Na-23, Al-27, and Ti-48. The HPGe Coaxial detector has been used to measure gamma rays emitted by nuclides in the sample. By the results, the proposed system can be an appropriate solution to measure the concentration and toxicity of elements in different samples such as food, soil, and plant samples.
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Three dimensional analysis of temperature effect on control rod worth in TRR
Maedeh Yari,Ahmad Lashkari,S. Farhad Masoudi,Mirshahram Hosseinipanah 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.8
In this paper, three-dimensional neutronic calculations were performed in order to calculate the dependencyof CRW on the temperature of fuel and moderator and the moderator void. Calculations wereperformed using the known MTR_PC computer codes in the core configuration 61 of TRR. The dependencyof CRW on the fuel temperature in the range of 20e340 C and the moderator temperature ofeach control rods were studied. Based on the positions of the control rods, the calculations were performedin three different cases, named case A, B and C. By the results, the worth of each control rodsincreases by increasing of the coolant temperature in all methods, however, the total CRW is somewhatindependent of the fuel temperature. In addition, the results showed that the variation of CRW versusdensity depends on the positions of the control rods and the most change in CRW in the coolant temperature,20e100 C (279 pcm), belongs to SR4. Finally the effect of void on CRW was studied fordifferent void fraction in coolant. The most worth change is about $2 for 40% void fraction related to SR1and SR3 in case B. For 40% void fraction, the total CRW increases about $7.5, $6 and $7 in cases, A, B and C,respectively
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