| Issue |
EPJ Web Conf.
Volume 153, 2017
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|
|
|---|---|---|
| Article Number | 05001 | |
| Number of page(s) | 3 | |
| Section | 5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning | |
| DOI | https://doi.org/10.1051/epjconf/201715305001 | |
| Published online | 25 September 2017 | |
https://doi.org/10.1051/epjconf/201715305001
Shielding and activation calculations around the reactor core for the MYRRHA ADS design
1 Helmholtz-Zentrum Dresden-Rossendorf, PF 910119, 01314 Dresden, Germany
2 SCK·CEN, Boretang 200, 2400 Mol, Belgium
3 ENEA, Via Martiri di Monte Sole 4, 40129 Bologna, Italy
a Corresponding author: a.ferrari@hzdr.de
Published online: 25 September 2017
In the frame of the FP7 European project MAXSIMA, an extensive simulation study has been done to assess the main shielding problems in view of the construction of the MYRRHA accelerator-driven system at SCK·CEN in Mol (Belgium). An innovative method based on the combined use of the two state-of-the-art Monte Carlo codes MCNPX and FLUKA has been used, with the goal to characterize complex, realistic neutron fields around the core barrel, to be used as source terms in detailed analyses of the radiation fields due to the system in operation, and of the coupled residual radiation. The main results of the shielding analysis are presented, as well as the construction of an activation database of all the key structural materials. The results evidenced a powerful way to analyse the shielding and activation problems, with direct and clear implications on the design solutions.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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