Data for: Monte Carlo Validation of dose mapping for the Tunisian gamma irradiation facility using MCNP6 code

Name: Data for: Monte Carlo Validation of dose mapping for the Tunisian gamma irradiation facility using MCNP6 code
Creator: Walid DRIDI
Published: 2020-05-06T20:47:23.998Z
Keywords: Error Analysis, Uncertainty Analysis

DRIDI, Walid; DAOUDI, Mahmoud; faouzi, Hosni; Farah, Khaled

doi:10.17632/4m6dyb6zss.1

Data for: Monte Carlo Validation of dose mapping for the Tunisian gamma irradiation facility using MCNP6 code

Published: 06-05-2020| Version 1 | DOI: 10.17632/4m6dyb6zss.1

Contributors:

Walid DRIDI,

Mahmoud DAOUDI,

Hosni faouzi,

Khaled Farah

Description

How to calculate the Root Mean Square Error between experimental data and MC simulations

Data for: Monte Carlo Validation of dose mapping for the Tunisian gamma irradiation facility using MCNP6 code

Description

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