The paper presents the main features of the Sn calculation sequence SCALENEA-1 that has been extensively used for radioactive inventories, source terms, wastes and dose rates calculation for ITER, SEAFP and IFMIF fusion machines. As part of the validation process for the code package and for the calculation sequence, experimental-calculation comparison has been performed using the information and the measured isotope radioactive inventories and dose rate gathered from drum containers of a low-level waste repository. The agreement between calculation and gamma dose rates experimental data is good: discrepancies are lower than 50%. To guarantee a complete Quality Assurance for codes and calculation scheme, a simulation of the radioactive containers to evaluate the dose rates has done also by using the Monte Carlo MCNP-4C code. The discrepancies between the two calculation approaches are lower than 1%. The conclusion of the study confirms once again that the SCALENEA-1 calculation sequence is able to provide reliable results for various fusion machines safety analyses purposes.

The SCALENEA-1 multipurpose Sn calculation sequence for application in fusion field: Main features and its validation based on experimental data from a low-level waste repository

Frisoni, M.;
2003

Abstract

The paper presents the main features of the Sn calculation sequence SCALENEA-1 that has been extensively used for radioactive inventories, source terms, wastes and dose rates calculation for ITER, SEAFP and IFMIF fusion machines. As part of the validation process for the code package and for the calculation sequence, experimental-calculation comparison has been performed using the information and the measured isotope radioactive inventories and dose rate gathered from drum containers of a low-level waste repository. The agreement between calculation and gamma dose rates experimental data is good: discrepancies are lower than 50%. To guarantee a complete Quality Assurance for codes and calculation scheme, a simulation of the radioactive containers to evaluate the dose rates has done also by using the Monte Carlo MCNP-4C code. The discrepancies between the two calculation approaches are lower than 1%. The conclusion of the study confirms once again that the SCALENEA-1 calculation sequence is able to provide reliable results for various fusion machines safety analyses purposes.
Tecnologie e metodologie diagnostiche
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/3484
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