engleski

Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART

In this work a Monte Carlo transport code named TART is engaged for total neutron buildup factors determination for NBS04 concrete type. The first step to model the total neutron buildup factors is to conduct a validation process of the TART code by calculating transmission factors for both neutrons and secondary photons. The transmission factors are then used for total ambient dose equivalent estimation. The direct component is calculated manually by using the exponential law, with the cross sections obtained from MCNP6. Finally, total ambient dose equivalent neutron buildup factor is calculated as the ratio of the total ambient dose equivalent and the direct component. The results are compared with the MCNP6 results. Obtained buildup factors are then embedded in a point kernel code named QAD- CGGP. A test case is modeled in TART, MCNP6 and QAD- CGGP and the results of the three codes are compared.

neutron buildup factor, transmission factors, ambient dose equivalent, TART, shielding

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