Experiences

Professional

 Designation :

Associate Professor 

University:

Isfahan Univ.  of Technology

Period:

1983-todate    

Nature of work:

Lab. supervision,  Undergraduate and Postgraduate teaching, Research & supervision.                      

Administration

· Chairman,Department of Physics(1985-1987)

· Administrator of Industrial Relations,Dept.of Physics(1990-1999)

· Deputy of Education,Faculty of Physics,(1999- January 2006)

· Chairman,Faculty of Physics,(January 2006-todate)

MSc thesis supervisions

    1- A study of potential energy of heavy and superheavy nuclei,

       by Mr.M.R.zahabi, Autumn 1997.

    2- Determination of response function for a NE213 scintillator

       by Monte-Carlo method,by Mr.A.Emamjomeh,March 1999.

    3-Calculation of buildup factors of gamma rays in water by

      Monte-Carlo method,by H.Esteki,March 1999.

    4-Determination of neutron spectrum in The Isfahan MNSR Reactor by

      foil activation,by Mr.H.Ghasemi,December 2001.

    5-Investigation of the effect of bremsstrahlung radiation on

      exposure buildup factors for gamma rays in lead by Monte-Carlo

      method,by Mr. A.Talaei,august 2003     

    6-Calculation of gamma-ray dose around the Isfahan HWZPR reactor

      using the MCNP computer code and comparison with experimental

      values ,by Ali Akbar Roohani,March 2004

    7-Calculation of gamma-ray exposure buildup factors for point

      sources in water and lead using the MCNP computer code,by

      Elham Jomebidokhti,February 2005    

    8-Determination of neutron dose equivalent buildup factors in

      water,iron and lead using the MCNP coputer code,by Esmail

      Shahriari,March 2005

    9-Calculation of gamma ray exposure build up factors in stratified

      Shields of water-lead using the MCNP computer code,

      By:A.Shakeri varzaneh ,March 2007

    10-Calculation of relative neutron flux in MNSR reactor using the

       MCNP computer code and comparison with experimental results,

       By: A.M.Niko ,April 2007

    11-Calculation of neutron flux distribution in the dry channel of

       The MNSR reactor using the MCNP code and comparison with

       experimental values.

       By: A.Sohrabi,March 2008

    12-Calculation of reactivity variation of the MNSR reactor due to

       variation in the thickness of the core top beryllium layer using

       the WIMS and MCNP codes and comparison with experimental results

       By: Leila Ranjbar,March 2009.

    13- Investigation of reactivity changes due to flooding of the MNSR

       inner irradiation sites using the MCNP code and comparison with

       experimental results.

       By: Hady Shamoradi,March 2010.

    14-Determination of thermal neutron flux for neutron sources in

       Graphite and water moderators using MCNP code and determination

       of the counting calibration coefficient of BF3 detectors.

       By: Hasan Vosoughian. , March 2010.

Teaching

Undergraduate Courses:

· Foundamentals of Physics(Phys1 & Phys2),

· Modern Physics,Electromagnetism,Nuclear

· Physics and Reactor Physics.

Postgraduate Courses:

·  Nuclear Physics

· Laboratory Supervision : Nuclear Physics Lab.

· Postgraduate Research Supervision