The present report outlines the results of new contributes to the 1D-Sn neutronics and activation calculation performed by ENEA in support of ITER safety analyses. They have been done in the frame of the EFDA Task No. TW4-TSS-SEA4.1. They were split in three parts: a) Updating and maintenance of the tools, libraries and procedures for 1-D radiation transport analysis and activation calculations. The new updated calculation approach SCALENEA-1 uses the VITENEA-J library, for radiation transport analyses, and both FISPACT-2003 or ANITA-2000, with EAF-2003 neutron activation library, for activation calculations. b) Calculation in support of ITER Primary Heat Transfer System ACPs assessment for Occupational Radiation Exposure evaluation. Updated Stainless Steel SS316 LN-IG inventories related to wet zones of ITER First Wall and Blanket coolant loops have been obtained in support of the activation characterization of the Activated Corrosion Products (ACPs). Moreover the impact of Cobalt content and of different irradiation scenarios on the coolant ACPs radioactive inventories were analysed. c) Examples of updated ITER in-vessel material activation characterisation. As applicative examples of the updated calculation approach, the activation characteristics of some ITER in-vessel outboard zones/materials have been obtained. The results obtained have been compared with those included into the Vol. III and V of GSSR. The results presented in this report point out once again the high flexibility of the SCALENEA-1 calculation sequence. It represents a very useful support in performing activation calculation for different purposes in safety analyses, particularly when fusion machine design is not yet frozen. Moreover it is also useful during design phases to perform parametric studies.

Summary report on the 2004 ENEA 1D-Sn neutronics and activation calculations for ITER

CAMBI, GILIO;
2004

Abstract

The present report outlines the results of new contributes to the 1D-Sn neutronics and activation calculation performed by ENEA in support of ITER safety analyses. They have been done in the frame of the EFDA Task No. TW4-TSS-SEA4.1. They were split in three parts: a) Updating and maintenance of the tools, libraries and procedures for 1-D radiation transport analysis and activation calculations. The new updated calculation approach SCALENEA-1 uses the VITENEA-J library, for radiation transport analyses, and both FISPACT-2003 or ANITA-2000, with EAF-2003 neutron activation library, for activation calculations. b) Calculation in support of ITER Primary Heat Transfer System ACPs assessment for Occupational Radiation Exposure evaluation. Updated Stainless Steel SS316 LN-IG inventories related to wet zones of ITER First Wall and Blanket coolant loops have been obtained in support of the activation characterization of the Activated Corrosion Products (ACPs). Moreover the impact of Cobalt content and of different irradiation scenarios on the coolant ACPs radioactive inventories were analysed. c) Examples of updated ITER in-vessel material activation characterisation. As applicative examples of the updated calculation approach, the activation characteristics of some ITER in-vessel outboard zones/materials have been obtained. The results obtained have been compared with those included into the Vol. III and V of GSSR. The results presented in this report point out once again the high flexibility of the SCALENEA-1 calculation sequence. It represents a very useful support in performing activation calculation for different purposes in safety analyses, particularly when fusion machine design is not yet frozen. Moreover it is also useful during design phases to perform parametric studies.
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D.G. Cepraga; G. Cambi; M. Frisoni
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/5884
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