The report presents the activation calculation results for all the materials/zones (from the centre void up to the biological shield) in the equatorial plane of ITER obtained using the EASY-2007 activation code package (with the EAF2007 activation data library). This has been done as a repetition of the calculation presented in previous ENEA reports (EFDA Task TW6-TSS-SEA4.1, Deliverables D3, D4 and D5) when the EASY-2005.1 activation code package (with the EAF2005.1 activation datalibrary) was used. Firstly, the case considered for GSSR (with the EAF99 activation data library) has been re-analysed (with the EAF2007 activation data library), showing a substantial agreement between the old and the new results for materials activity, decay heat and contact dose rate. Instead, a significant difference has been found for the material unconditional clearance index, due to the different data libraries used to calculate that material activation parameter. Then the three Cases defined as follow have been analysed: Case1): Increase of the average neutron fluence on the ITER First Wall from 0.5 (i.e. the GSSR value) to 1.0 MWa/m2, based on an irradiation scenario defined by ITER and provided by EFDA. All the other design assumptions must be the same as for GSSR. Beryllium is considered as First Wall protective layer. Case 2): Tungsten instead of Be as it was considered for FW PFC in GSSR. The irradiation scenario SA1 used for ITER GSSR is considered (i.e. ITER First wall average fluence is 0.5 MWa/m2). All the other design assumptions must be the same as for GSSR. Case 3): Tungsten instead of Beryllium as it was considered for FW PFC in GSSR. The irradiation scenario is the SA1-extended (defined by ITER and provided by EFDA, to reach an ITER First wall average fluence of 1.0 MWa/m2) and used also for the Case 1) analysis. All the other design assumptions must be the same as for GSSR. A discussion of the results obtained for those three Cases is in the report. The answer to the main goals of the Task: a) comparison of the results of the new activation calculation with those included in ITER GSSR and b) implication of those updated calculation results on the ITER Preliminary Safety Report (RPrS) writing are presented and discussed respectively into the Sections 3 and 4 of the present report, both when EASY-2005.1 and EASY-2007 are used for the calculations.

ITER 2007 activation calculations: understanding comparison with GSSR and implication on RPrS writing

CAMBI, GILIO;
2008

Abstract

The report presents the activation calculation results for all the materials/zones (from the centre void up to the biological shield) in the equatorial plane of ITER obtained using the EASY-2007 activation code package (with the EAF2007 activation data library). This has been done as a repetition of the calculation presented in previous ENEA reports (EFDA Task TW6-TSS-SEA4.1, Deliverables D3, D4 and D5) when the EASY-2005.1 activation code package (with the EAF2005.1 activation datalibrary) was used. Firstly, the case considered for GSSR (with the EAF99 activation data library) has been re-analysed (with the EAF2007 activation data library), showing a substantial agreement between the old and the new results for materials activity, decay heat and contact dose rate. Instead, a significant difference has been found for the material unconditional clearance index, due to the different data libraries used to calculate that material activation parameter. Then the three Cases defined as follow have been analysed: Case1): Increase of the average neutron fluence on the ITER First Wall from 0.5 (i.e. the GSSR value) to 1.0 MWa/m2, based on an irradiation scenario defined by ITER and provided by EFDA. All the other design assumptions must be the same as for GSSR. Beryllium is considered as First Wall protective layer. Case 2): Tungsten instead of Be as it was considered for FW PFC in GSSR. The irradiation scenario SA1 used for ITER GSSR is considered (i.e. ITER First wall average fluence is 0.5 MWa/m2). All the other design assumptions must be the same as for GSSR. Case 3): Tungsten instead of Beryllium as it was considered for FW PFC in GSSR. The irradiation scenario is the SA1-extended (defined by ITER and provided by EFDA, to reach an ITER First wall average fluence of 1.0 MWa/m2) and used also for the Case 1) analysis. All the other design assumptions must be the same as for GSSR. A discussion of the results obtained for those three Cases is in the report. The answer to the main goals of the Task: a) comparison of the results of the new activation calculation with those included in ITER GSSR and b) implication of those updated calculation results on the ITER Preliminary Safety Report (RPrS) writing are presented and discussed respectively into the Sections 3 and 4 of the present report, both when EASY-2005.1 and EASY-2007 are used for the calculations.
51
G. Cambi; D.G. Cepraga
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/69495
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