The objective of this work is to analyze the differences between the experimentally measured and calculated doses from particle transport simulation using point-like detector option in the Monte Carlo MCNPX code. In the radial channel # 3 (BH # 3) at the IEA-R1 nuclear research reactor of Instituto de Pesquisas Energeticas e Nucleares (IPEN) in Brazil, biological samples were irradiated with the reactor in operation. To estimate radiation damage in the sample, it was necessary to determine the deposited dose in the irradiation position.

Uncertainties in dose calculations in mixed radiation field using point-like detector option in the MCNPX code / Gual, M. R.; Vega Carrillo, H. R.; Zucchetti, Massimo; Mas, F.. - In: TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY. - ISSN 0003-018X. - STAMPA. - 102:(2010), pp. 473-474.

Uncertainties in dose calculations in mixed radiation field using point-like detector option in the MCNPX code

ZUCCHETTI, MASSIMO;
2010

Abstract

The objective of this work is to analyze the differences between the experimentally measured and calculated doses from particle transport simulation using point-like detector option in the Monte Carlo MCNPX code. In the radial channel # 3 (BH # 3) at the IEA-R1 nuclear research reactor of Instituto de Pesquisas Energeticas e Nucleares (IPEN) in Brazil, biological samples were irradiated with the reactor in operation. To estimate radiation damage in the sample, it was necessary to determine the deposited dose in the irradiation position.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11583/2422938
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