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RISS 인기검색어
- 검색키워드
- 저자 : Khoshahval, F. (검색결과 4 건)
- 무료
- 기관 내 무료
- 유료
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Akbari, M.,Khoshahval, F.,Minuchehr, A.,Zolfaghari, A. Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.7
Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that $UO_2-PuO_2$ (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the $UO_2$ fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of $H_2O$ moderated $UO_2-PuO_2$ (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.
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Amirkhani, Mohamad Amin,Khoshahval, Farrokh Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.12
Radiation damage is one of the aging important causes in nuclear reactors. Radiation damage causes changes in material properties. In this study, this effect has been evaluated and analyzed on the clad of the Tehran research reactor (TRR). A grade 6061 aluminum is used as a clad in the TRR. The MCNPX code is used to designate the most sensitive location of the reactor and calculate neutron flux distribution. Then, a software using FORTRAN language programming is developed to process the particle track (PTRAC) output file of the MCNPX code. The SRIM code is used here to calculate the rate of displacement per atom. Moreover, the SPECOMP and SPECTER codes are also applied to estimate the displacement rate and compared with the results attained using the SRIM code. The rate of displacement per atom by the SPECTER and SRIM codes have been obtained 2.54 × 10<sup>-7</sup> dpa/s and 2.44 × 10<sup>-7</sup> dpa/s (QD method), respectively. Also, the mechanical properties have been evaluated using the RCC-MRx code and have been compared with experimental results. Finally, the change in the matter specification has been analyzed as a function of time.
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M. AKBARI,F. Khoshahval,A. Minuchehr,A. Zolfaghari 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.7
Energy group structure has a significant effect on the results of multigroup transport calculations. It is known thatUO2–PuO2 (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains variousresonant nuclides, the selection of energy group structure is more crucial comparing to the UO2 fuels. In this paper, in order toimprove the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligencemethod is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used togenerate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor andspectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy groupstructure. Calculations performed in four different types of H2O moderated UO2–PuO2 (MOX) lattices show that the optimizedenergy structure obtains more accurate results in comparison with the WIMS original structure.
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Moslemi-Mehni Elaheh,Khoshahval Farrokh,Pour-Imani Reza,Amirkhani-Dehkordi M.A. 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.9
Due to neutron radiation, atomic displacement has a significant effect on material in nuclear reactors. A range of secondary displacement models, including the Kinchin-Pease (KeP), Lindhard, NorgettRobinson-Torrens (NRT), and athermal recombination-corrected displacement per atom (arc-dpa) have been suggested to calculate the number of displacement per atom (dpa). As neutron elastic interaction is the main cause of displacement damage, the focus of the current study is to calculate the atomic displacement caused by the neutron elastic interaction in order to estimate the exact amount of yield strength in a WWER-1000 reactor pressure vessel. To achieve this purpose, the reactor core is simulated by MCNPX code. In addition, a program is developed to calculate the elastic radiation damage induced by the incident neutron flux (RADIX) based on different models using Fortran programming language. Also, due to non-elastic interaction, the displacement damage is calculated by the HEATR module of the NJOY code. ASME E-693-01 standard, SPECTER, NJOY codes, and other pervious findings have been used to validate RADIX results. The results showed that the RADIX(arc-dpa)/HEATR outputs have appropriate accuracy. The relative error of the calculated dpa resulting from RADIX(arc-dpa)/HEATR is about 8% and 46% less than NJOY code, respectively in the ¼ and ¾ vessel wall.
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