Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.018 seconds
AbstractAbstract
[en] In the unlikely event of core disruptive accident in sodium cooled fast reactors, the reactor containment building would be bottled up with sodium and fission product aerosols. The behavior of these aerosols is crucial to estimate the in-containment source term as a part of nuclear reactor safety analysis. In this work, the evolution of sodium aerosol characteristics (mass concentration and size) is simulated using HAARM-S code. The code is based on the method of moments to solve the integro-differential equation. The code is updated to FORTRAN-77 and run in Microsoft FORTRAN PowerStation 4.0 (on Desktop). The sodium aerosol characteristics simulated by HAARM-S code are compared with the measured values at Aerosol Test Facility. The maximum deviation between measured and simulated mass concentrations is 30% at initial period (up to 60 min) and around 50% in the later period. In addition, the influence of humidity on aerosol size growth for two different aerosol mass concentrations is studied. The measured and simulated growth factors of aerosol size (ratio of saturated size to initial size) are found to be matched at reasonable extent. Since sodium is highly reactive with atmospheric constituents, the aerosol growth factor depends on the hygroscopic growth, chemical transformation and density variations besides coagulation. Further, there is a scope for the improvement of the code to estimate the aerosol dynamics in confined environment
Primary Subject
Source
26 refs, 4 figs, 3 tabs
Record Type
Journal Article
Journal
Nuclear Engineering and Technology; ISSN 1738-5733; ; v. 54(6); p. 2077-2083
Country of publication
ABUNDANCE, AEROSOLS, COMBUSTION, CONTAINMENT BUILDINGS, CRYSTAL GROWTH, DENSITY, ENVIRONMENT, EVOLUTION, FISSION PRODUCTS, HUMIDITY, INTEGRO-DIFFERENTIAL EQUATIONS, MOMENTS METHOD, REACTOR CORE DISRUPTION, REACTOR SAFETY, S CODES, SAFETY ANALYSIS, SODIUM COOLED REACTORS, SOURCE TERMS, TEST FACILITIES
ACCIDENTS, BEYOND-DESIGN-BASIS ACCIDENTS, BUILDINGS, CALCULATION METHODS, CHEMICAL REACTIONS, COLLOIDS, COMPUTER CODES, CONTAINMENT, DISPERSIONS, EQUATIONS, ISOTOPES, LIQUID METAL COOLED REACTORS, MATERIALS, MOISTURE, OXIDATION, PHYSICAL PROPERTIES, RADIOACTIVE MATERIALS, REACTOR ACCIDENTS, REACTORS, SAFETY, SEVERE ACCIDENTS, SOLS, THERMOCHEMICAL PROCESSES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue