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  1. Nurin Irdina Binti Mohd Anuar, Asyraf Arif, Abdul Aziz Mohamed, Mohamad Hairie Rabir, Faridah Mohamad Idris, Muhammad Rawi Md Zin
    MyJurnal
    In order to prepare Malaysia to be nuclear ready, the Malaysian 1 MW TRIGA MARK II research
    reactor (RTP) located at the Malaysian Nuclear Agency was premeditated with the aim to effectually
    actualize the multitude areas of basic nuclear research, labor training and education. To meet the
    modern safety standards, analyses of a strong interaction between the thermal-hydraulic system
    behavior and the space-dependent neutron kinetics are needed as mere thermal-hydraulics codes are
    said to be incapable to succeed the present safety standards. This could be achieved through the
    coupling of neutronic and thermal-hydraulic codes of the reactor. Previous studies had shown that the
    coupled codes are able to successfully be employed for the correlation between thermal-hydraulic
    analysis and neutron kinetics at transient and steady state. In this study, the coupling was achieved
    through MCNP and TRIGLAV codes for neutronic and thermal-hydraulic respectively. Core-15 of
    RTP was modeled for both of the codes; hence calculating the criticality, analysis of power and
    neutron flux distribution. The consistency and accuracy of the developed Core-15 MCNP model was
    established by comparing calculations to the experimental results and TRIGLAV code. The criticality
    predictions for both codes are in very good agreement with the experimental results. The core reached
    its criticality after 66 fuels. The highest hot rod power peaking factor was found to be 1.28. The
    results are conservative and can be applied to show the reliability of MCNP and TRIGLAV codes.
  2. Mohd Rafi Mohd Solleh, Abdul Aziz Mohamed, Abd. Aziz Tajuddin, Faridah Idris, Mohamad Hairie Rabir, Muhammad Rawi Md Zin, et al.
    MyJurnal
    Thermal neutron beam from thermal column was selected for a Boron Neutron Capture Therapy
    (BNCT) system utilizing the Malaysian TRIGA MARK II reactor. Determination of shielding
    materials for fast and epithermal neutron was conducted. The materials selected were polyethylene,
    paraffin and water. For gamma-ray shielding, lead was used. The objective of this paper is to present
    the simulation and verification of an optimal design of BNCT collimation at a beam. line viewing the
    thermal column. A collimator was made from polyethylene pipe with 8 cm of diameter filled with
    paraffin.
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