Mojtaba Tajik

Assistant Professor of Nuclear Physics

  • TEL: +98-2335220090
  • Google Scholar
  • Teaching

    • Reactor Physic
    • Nuclear Physics I,II
    • Electromagnetism I,II
    • Electrodynamics
    • Radiation detection and measurement

    Selected Publications

    Tajik, M., Yousefnia, H. Comparison of the FLUKA and MCNPX codes in calculation of response function of organic scintillators to gamma rays and neutrons (2018) 17 (5), pp. 635-645.

    In organic scintillators, the energy distribution of gamma rays and neutrons is indirectly measured by the pulse height distribution of light output produced through gamma ray and neutron reactions in the detectors. Accurate estimate of the interaction of gamma and neutrons in the detector and produce charged secondary particles and subsequent scintillation light produced in the calculation of the response function is the most important. Although, the complexity of the light generation on these scintillators makes modeling their response function difficult with standard Monte Carlo method. The paper reports generate the response function of an NE102 plastic scintillator when exposed to gamma rays and response function of a BC501A liquid scintillator to mono-energetic and Am-Be neutrons using the EVENTBIN card of the FLUKA code and the PTRAC card of the MCNPX code. The comparison between simulated and experimental response functions show that both FLUKA and MCNPX codes generated distributions are in good agreement with corresponding experimental results. © 2018, Isfahan University of Technology. All rights reserved.

    AUTHOR KEYWORDS: FLUKA; MCNPX; Neutrons; Organic scintillators; Response function
    PUBLISHER: Isfahan University of Technology

    Tajik, M., Ghal-Eh, N. Comparison of light transport-incorporated MCNPX and FLUKA codes in generating organic scintillators responses to neutrons and gamma rays (2015) 791, pp. 65-68.

    DOI: 10.1016/j.nima.2015.04.043

    The NE102 plastic scintillator response to 137Cs gamma rays and NE213 liquid scintillator response to both mono-energetic and 241Am-Be neutrons have been modeled using FLUKA's EVENTBIN and MCNPX's PTRAC cards. The comparison made in different energy regions confirms that the overall difference is less than 6%. © 2015 Elsevier B.V.

    AUTHOR KEYWORDS: MCNPX FLUKA PHOTRACK Scintillator Response Efficiency
    INDEX KEYWORDS: Scintillation counters, Comparison of lights; Energy regions; FLUKA codes; Liquid scintillator; Organic scintillator; Plastic scintillator; Response efficiencies, Gamma rays
    PUBLISHER: Elsevier

    Yousefnia, H., Zolghadri, S., Jalilian, A.R., Tajik, M., Ghannadi-Maragheh, M. Preliminary dosimetric evaluation of 166Ho-TTHMP for human based on biodistribution data in rats (2014) 94, pp. 260-265.

    DOI: 10.1016/j.apradiso.2014.08.017

    In this work, the absorbed dose to each organ of human for 166Ho-TTHMP was evaluated based on biodistribution studies in rats by a RADAR method and was compared with 166Ho-DOTMP as the only clinically used Ho-166 bone marrow ablative agent. The highest absorbed dose for this complex is observed in red marrow with 0.922mGy/MBq. The results show that 166Ho-TTHMP has considerable characteristics compared to 166Ho-DOTMP and can be a good candidate for bone marrow ablation in patients with multiple myeloma. © 2014 Elsevier Ltd.

    AUTHOR KEYWORDS: 166Ho-TTHMP; Bone marrow ablation; Internal dosimetry; RADAR
    INDEX KEYWORDS: 166Ho-TTHMP; Biodistributions; Bone marrow, Radar, antineoplastic agent; holmium DOTMP ho 166; holmium triethylene tetramine hexa(methylene phosphonic acid) ho 166; radiopharmaceutical agent; unclassified drug; edetic acid; holmium; radioisotope; radiopharmaceutical agent; triethylenetetraminehexaacetic acid, animal experiment; animal tissue; Article; controlled study; dosimetry; drug clearance; drug distribution; drug purity; drug synthesis; drug tissue level; nonhuman; quality control; radiation absorption; radiation dose distribution; rat; tissue distribution; analogs and derivatives; animal; antibody specificity; biological model; bone marrow; computer simulation; human; metabolic clearance rate; metabolism; pilot study; procedures; radiation dose; species difference; whole body counting, Absorption, Radiation; Animals; Bone Marrow; Computer Simulation; Edetic Acid; Holmium; Humans; Metabolic Clearance Rate; Models, Biological; Organ Specificity; Pilot Projects; Radiation Dosage; Radioisotopes; Radiopharmaceuticals; Rats; Species Specificity; Tissue Distribution; Whole-Body Counting
    PUBLISHER: Elsevier Ltd

    Tajik, M., Ghal-Eh, N., Etaati, G.R., Afarideh, H. NE213/BC501A scintillator-lightguide assembly response to 241Am-Be neutrons: An MCNPX-PHOTRACK hybrid code simulation (2014) 97, pp. 319-324.

    DOI: 10.1016/j.radphyschem.2013.12.011

    The response of an NE213 (or its BICRON equivalent, BC501A) scintillator attached to different sizes of polished/painted lightguides when exposed to 241Am-Be neutrons has been simulated. This kind of simulation basically needs both particle and light transports: the transport of neutrons and neutron-induced charged particles such as alphas, protons, carbon nuclei and so on has been undertaken using MCNPX whilst the scintillation light transport has been performed with PHOTRACK codes. The comparison between simulated and experimental response functions of NE213 attached to different sizes of polished/painted lightguides and also the influence of length/covering of lightguide on the detection efficiency and uniformity of the scintillator-lightguide assembly response have been studied. © 2013 Elsevier Ltd.

    AUTHOR KEYWORDS: 241Am-Be; MCNPX; Neutron; PHOTRACK; Response; Scintillator
    INDEX KEYWORDS: 241Am-Be; Detection efficiency; Light transport; MCNPX; PHOTRACK; Response; Response functions; Scintillation light, Neutrons; Phosphors, Scintillation counters, americium 241; beryllium, article; intermethod comparison; light collection efficiency; light collection uniformity; light related phenomena; light transport; MCNPX PHOTRACK hybrid code; Monte Carlo method; NE213 scintillator; neutron radiation; process model; proton transport; radiation detection; radiation equipment; radiological parameters; response variable; scintillator lightguide assembly; simulation

    Tajik, M., Ghal-Eh, N., Etaati, G.R., Afarideh, H. Modeling NE213 scintillator response to neutrons using an MCNPX-PHOTRACK hybrid code (2013) 704, pp. 104-110.

    DOI: 10.1016/j.nima.2012.12.001

    This paper reports on how to generate the response function of an NE213 scintillator when exposed to mono-energetic neutrons using the PTRAC card of the MCNPX code. The light transport part of the simulation has been undertaken with the Monte Carlo PHOTRACK code. The comparison confirms that the simulated response function represents a promising agreement with the previously published simulations and experiments. © 2012 Elsevier B.V.

    AUTHOR KEYWORDS: MCNPX; Neutron; PHOTRACK; Response function; Scintillator
    INDEX KEYWORDS: Light transport; MCNPX; MCNPX code; Mono-energetic neutrons; MONTE CARLO; NE213 scintillator; PHOTRACK; Response functions; Simulated response, Neutrons; Phosphors, Monte Carlo methods