EPJ Web Conf.
Volume 153, 2017ICRS-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
|Number of page(s)||7|
|Section||5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning|
|Published online||25 September 2017|
Methodology for the nuclear design validation of an Alternate Emergency Management Centre (CAGE)
1 Idom Ingeniería y Consultoría, Avda. Zarandoa, 23 Bilbao-Vizcaya Spain 48015, +34 944797600
2 ANAV Asociación Nuclear Ascó-Vandellòs II, L’Hospitalet de l’Infant-Tarragona Spain 43890, +34 977818800
3 Fusion for Energy, C/Josep Pla, 2, Torres Diagonal Litoral, Edif. B3 Barcelona Spain 08019, +34 933201800
* Corresponding author: email@example.com
Published online: 25 September 2017
The methodology is devised by coupling different codes. The study of weather conditions as part of the data of the site will determine the relative concentrations of radionuclides in the air using ARCON96. The activity in the air is characterized depending on the source and release sequence specified in NUREG-1465 by RADTRAD code, which provides results of the inner cloud source term contribution. Known activities, energy spectra are inferred using ORIGEN-S, which are used as input for the models of the outer cloud, filters and containment generated with MCNP5. The sum of the different contributions must meet the conditions of habitability specified by the CSN (Spanish Nuclear Regulatory Body) (TEDE <50 mSv and equivalent dose to the thyroid <500 mSv within 30 days following the accident doses) so that the dose is optimized by varying parameters such as CAGE location, flow filtering need for recirculation, thicknesses and compositions of the walls, etc. The results for the most penalizing area meet the established criteria, and therefore the CAGE building design based on the methodology presented is radiologically validated.
© The Authors, published by EDP Sciences, 2017
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