Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code
- 1. KAERI, Daejeon (Korea, Republic of)
- 2. Fauske & Associates, LLC, Burr Ridge (United States)
Description
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
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 53
- Journal Issue
- 12
- Series
- 22 refs, 7 figs, 7 tabs
- Journal Page Range
- p. 3966-3978
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 53091559
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AEROSOLS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; CORRELATIONS; EXPERIMENTAL DATA; FISSION PRODUCTS; FORECASTING; I CODES; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ANALYSIS; SODIUM COOLED REACTORS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COLLOIDS; COMPUTER CODES; DATA; DISPERSIONS; INFORMATION; ISOTOPES; LIQUID METAL COOLED REACTORS; MATERIALS; NUMERICAL DATA; RADIOACTIVE MATERIALS; REACTORS; SAFETY; SIMULATION; SOLS; TESTING