Neutron and Gamma dosimetry of the designed and installed shielding of TRR D channel

، صفحه 0-0 (1)
عنوان دوره: اولین دوره بین المللی و بیست و هشتمین دوره ملی (1400)
Neutron beam ports in research reactors are installed for facilities such as neutron scattering, neutron activation analysis (NAA) and neutron radiography. In addition to the main shield installed on the beam ports, the research reactor hall partitioning is mainly required to limit the occupation around the neutron analysis systems because of the high neutron and gamma dose rates around the shield; especially when the system is under operation. In the present work, neutron and gamma dose rate mapping around the main shield of D channel of Tehran Research Reactor (TRR) was calculated using MCNPX code. In order to accomplish a benchmark study, some measurements were carried out. Comparison between the simulation and measurement data showed there is good conformity and acceptable relative discrepancy. Also the obtained neutron and gamma dose mapping data showed there is a necessity for partitioning around the shield so that after the possible material for partitioning the summation of neutron and gamma dose rates could be reduced to less than 7.5 μSv/h.
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