TAILIEUCHUNG - Methodology for the nuclear design validation of an Alternate Emergency Management Centre (CAGE)

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. | Methodology for the nuclear design validation of an Alternate Emergency Management Centre CAGE EPJ Nuclear Sci. Technol. 3 5 2017 Nuclear Sciences C. Hueso et al. published by EDP Sciences 2017 amp Technologies DOI epjn 2017004 Available online at http REGULAR ARTICLE Methodology for the nuclear design validation of an Alternate Emergency Management Centre CAGE César Hueso1 Marco Fabbri1 3 Cristina de la Fuente1 Albert Janés1 Joan Massuet1 Imanol Zamora1 Cristina Gasca2 Héctor Hernández2 and J. Ángel Vega2 1 Idom Ingeniería y Consultoría Avda. Zarandoa 23 Bilbao-Vizcaya 48015 Spain 2 ANAV Asociación Nuclear Ascó-Vandellòs II L Hospitalet de l Infant Tarragona 43890 Spain 3 Fusion for Energy C Josep Pla 2 Torres Diagonal Litoral Edif. B3 Barcelona 08019 Spain Received 18 November 2016 Accepted 30 January 2017 Abstract. 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 and 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 2 C. Hueso et al. EPJ Nuclear Sci. Technol. 3 5 2017 X Q Meteorological ARCON96 0 Outer cloud model records Accident parameters MCNP Dose rate calcula on Outer cloud ORIGEN-S Core isotopic Gamma energy inventory RADTRAD Released ac vity spectrum calcula on MCNP Dose rate calcula on Containment Mi ga ons Inner cloud dose rate calcula on inside CAGE ORIGEN-S HEPA amp AC gamma MCNP HVAC System Dose rate calcula on energy spectrum .

• Năng lượng
• Spanish Nuclear Regulatory Body
• CAGE building design
• Alternate Emergency Management Centre
• Nuclear design validation
• Monte Carlo radiation transport calculation