Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code

• Published in: Nuclear engineering and technology Vol. 53; no. 12; pp. 3966 - 3978
• Main Authors: Yoon, Churl, Kim, Sung Il, Lee, Sung Jin, Kang, Seok Hun, Paik, Chan Y
• Format: Journal Article
• Language: Korean
• Published: 2021
• Subjects: Sodium-cooled fast reactor (SFR); Log-normal distribution; Severe accident; Fission product; Aerosols
• ISSN: 1738-5733; 2234-358X

ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident. This paper describes validation of the ISFRA aerosol model against the Aerosol Behavior Code Validation and Evaluation (ABCOVE) experiments undertaken in 1980s for radionuclide transport within a SFR containment. ABCOVE AB5, AB6, and AB7 tests are simulated using the ISFRA aerosol model and the results are compared against the measured data as well as with the simulation results of the MELCOR severe accident code. It is revealed that the ISFRA prediction of single-component aerosols inside a vessel (AB5) is in good agreement with the experimental data as well as with the results of the aerosol model in MELCOR. Moreover, the ISFRA aerosol model can predict the "washout" phenomenon due to the interaction between two aerosol species (AB6) and two-component aerosols without strong mutual interference (AB7). Based on the theory review of the aerosol correlation technique, it is concluded that the ISFRA aerosol model can provide fast, stable calculations with reasonable accuracy for most of the cases unless the aerosol size distribution is strongly deformed from log-normal distribution.