Sharif University of Technology

Department of Energy Engineering

 

Personal Details

Seyed Abolfazl Hosseini

 Assistant Professor

Contact Information

Postal Address:

Department of Energy Engineering, Sharif University of Technology, Tehran, Iran

Phone Numbers:

Work: +98 21 6616 6107(Office)

E-mail: sahosseini At sharif.edu,

Statement of Research Interests

Current Courses

Publications

 A-Journal papers (ISI)

  1. Hosseini, S.A., Vosoughi, N., Ghofrani, M.B., and Gharib, M., 2010., Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor., Annals of Nuclear Energy, 37, pp. 463-470.

  2. Hosseini, S.A., Vosoughi, N., 2010., Uncertainty evaluation of calculated and measured kinetics parameters of Tehran Research Reactor. Nuclear Engineering and Design, 240, pp. 2761-2767.

  3.  Hosseini, S.A., Vosoughi, N and  Hosseini, M.,  2011., Monte Carlo simulation of Feynman-alpha and Rossi-alpha techniques for calculation of kinetic parameters of Tehran Research Reactor. Annals of Nuclear Energy, 5, pp. 2140–2145.

  4. Hosseini, S.A., Vosoughi, N., 2012., Neutron noise simulation by GFEM and unstructured triangle elements. Nuclear Engineering and Design, 253, pp. 238-258.

  5. Hosseini, S.A., Vosoughi, N., 2013. Development of two-dimensional, multigroup neutron diffusion computer code based on GFEM with unstructured triangle elements. Annals of Nuclear Energy, 51, pp. 213-226.

  6. Hosseini, S.A., Vosoughi, N., 2013. On a various source reconstruction algorithms in VVER-1000 reactor core. Nuclear Engineering and Design, 261, pp. 132-143.

  7. Hosseini, S.A., Vosoughi, N., 2014. Noise source reconstruction using ANN and hybrid methods in VVER-1000 reactor core. Progress in Nuclear Energy, 71, pp. 232-247.

  8. Hosseini, S.A., Vosoughi, N., Zangian, M., 2015. Development of MCNPX-ESUT computer code for simulation of neutron/gamma pulse height distribution. Nuclear Instrument and Methods in Physics Research A, 782,pp. 112-119.

  9. Hosseini, S.A., Saadatian, F., 2015. Galerkin and Generalized Least Squares finite element: A comparative study for multi-group diffusion solvers. Progress in Nuclear Energy, 85, pp.473-490.

  10. Shahbinejad, H., Hosseini, S.A., Sohrabpour, M., 2016.  A new neutron energy spectrum unfolding code using a two steps genetic algorithm. Nuclear Instrument and Methods in Physics Research A, 811,pp. 82-93.

  11. Hosseini, S.A., 2016. Neutron spectrum unfolding using artificial neural network and modified least square method. Radiation Physics and Chemistry, 126, pp. 75-84.

  12. Hosseini, S.A., 2016. Development of Galerkin Finite Element Method Three-dimensional Computational Code for the Multigroup Neutron Diffusion Equation with Unstructured Tetrahedron Elements. Nuclear Engineering and Technology, 48, pp.43-54.

  13. Hosseini, S.A., 2016. 3D neutron diffusion computational code based on GFEM with unstructured tetrahedron elements: A comparative study for linear and quadratic approximations. Progress in Nuclear Energy, 92, pp.119-132.

  14. Hosseini, S.A., Vosoughi, N., 2016. Development of 3D neutron noise simulator based on GFEM with unstructured tetrahedron elements. Annals of Nuclear Energy, 97, pp. 132-141.

  15. Hosseini, S.A., 2016. Sensitivity Analysis of the Galerkin Finite Element Method Neutron Diffusion Solver to the Shape of the Elements. Nuclear Engineering and Technology, 49, pp.29-42.

  16. Hosseini, S.A., Esmaili Paeen Afrakoti, I., 2017. Energy spectra unfolding of fast neutron sources using the group method of data handling and decision tree algorithms. Nuclear Instrument and Methods in Physics Research A, 851,pp. 5-9.

  17. Hosseini, S.A., Esmaili Paeen Afrakoti, I., 2017. Neutron noise source reconstruction using the Adaptive Neuro-Fuzzy Inference System (ANFIS) in the VVER-1000 reactor core. Annals of Nuclear Energy, 105, pp. 36-44.

  18. Zamzamian, S. M., Hosseini, S.A., Samadfam, M., 2017. Optimization of the marinelli beaker dimensions using genetic algorithm. Journal of Environmental Radioactivity, 172, pp. 81-88.

  19. Hosseini, S.A., Esmaili Paeen Afrakoti, I., 2017. Adaptive group of ink drop spread: a computer code to unfold neutron noise sources in reactor cores. Nuclear Engineering and Technology, xxx, pp.1-10.

  20. Ayyoubzadeh, S.M., Hosseini, S.A., Vosoughi, N., 2017. Higher order power reactor noise analysis: The multigroup diffusion model. Annals of Nuclear Energy, 111, pp. 354-370.

B- International Conference Papers

  1. Hosseini, S.A., Vosoughi, N., Ghofrani, M.B., and Gharib, M., 2009.  Calculation and measurement of kinetic parameters of Tehran Research Reactor. Proceeding of the 17th International Conference on Nuclear Engineering- ICONE17-75036.

  2. Hosseini, S.A., Vosoughi, N., 2009. Sensitivity analysis of kinetic parameters of Tehran Research Reactor Proceeding of the 17th International Conference on Nuclear Engineering- ICONE17-75523.

  3. Hosseini, M., Vosoughi, N., Hosseini, S.A., 2010., Co ntrol Rod Worth Calculation for Tehran Research Reactor (TRR) using MCNP4C Code., Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNS +MC2010).

  4. Hosseini, S.A., Vosoughi, N., Hosseini, M., 2011. Monte Carlo simulation of Feynman-alpha and Rossi-alpha techniques for calculation of kinetic parameters of Tehran Research Reactor. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) Rio de Janeiro, RJ, Brazil, May 8-12, 2011, on CD-ROM, Latin American Section (LAS) / American Nuclear Society (ANS) ISBN 978-85-63688-00-2.

  5. Khodajou-Chokami, H., Vosoghi-vahdat, B., Hosseini, S.A., 2017. Quantitative assessment of patient does and image quality in mammography systems using monte-carlo method. 2th International Conference on Electrical Engineering, Allameh Tabatabai University, Tehran, Iran.

B- C. National Conference Papers

  1. 1.       سيد ابوالفضل حسيني و ناصر وثوقي، آناليز حساسيت پارامترهاي سينتيکي راکتور تحقيقاتي تهران، کنفرانس هسته اي ايران، گرگان، اسفند 87.

    2.       سيد ابوالفضل حسيني و ناصر وثوقي، توسعه شبیه ساز نویز نوترونی دو گروهی - یک بعدی با استفاده از روش عناصر محدود، کنفرانس هسته اي ايران، یزد، اسفند 90.

    3.       سید ابوالفضل حسینی و ناصر وثوقی. بازسازی چشمه نویز نوترونی با استفاده ار روش پویشی در راکتور VVER-1000. کنفرانس هسته ای ایران، مشهد، اسفند 91.

    4.       سجاد آقابزرگی، ناصر وثوقی و  سید ابوالفضل حسینی. استفاده از روش خوشه بندی برای جداسازی دیجیتال تپهای نوترون و پرتوی گاما. کنفرانس هسته ای ایران، اصفهان، اسفند 93.

    5.      جواد وثوقی،  سید ابوالفضل حسینی و ناصر وثوقی. شبیه¬سازی نویز نوترونی ناشی از بارگذاری اشتباه دو مجتمع سوخت مجاور هم به روش نودال بسط شار. کنفرانس هسته ای ایران، تهران، اسفند 95.