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RISS 인기검색어
- 검색키워드
- 저자 : Usha Pujala (검색결과 2 건)
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Sujatha Pavan Narayanam,Amit Kumar,Usha Pujala,Subramanian V.,Srinivas C.V.,Venkatesan R.,Athmalingam S.,Venkatraman B. 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.6
In the unlikely event of core disruptive accident in sodium cooled fast reactors, the reactor containmentbuilding would be bottled up with sodium and fission product aerosols. The behavior of these aerosols iscrucial to estimate the in-containment source term as a part of nuclear reactor safety analysis. In thiswork, the evolution of sodium aerosol characteristics (mass concentration and size) is simulated usingHAARM-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). Thesodium aerosol characteristics simulated by HAARM-S code are compared with the measured values atAerosol Test Facility. The maximum deviation between measured and simulated mass concentrations is30% at initial period (up to 60 min) and around 50% in the later period. In addition, the influence ofhumidity on aerosol size growth for two different aerosol mass concentrations is studied. The measuredand simulated growth factors of aerosol size (ratio of saturated size to initial size) are found to bematched at reasonable extent. Since sodium is highly reactive with atmospheric constituents, the aerosolgrowth 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 aerosoldynamics in confined environment
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A study on transport and plugging of sodium aerosol in leak paths of concrete blocks
Narayanam Sujatha Pavan,Sen Soubhadra,Kumari Kalpana,Kumar Amit,Pujala Usha,Subramanian V.,Chandrasekharan S.,Preetha R.,Venkatraman B. 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.1
In the event of a severe accident in Sodium Cooled Fast Reactors (SFR), the sodium combustion aerosols along with fission product aerosols would migrate to the environment through leak paths of the Reactor Containment Building (RCB) concrete wall under positive pressure. Understanding the characteristics of sodium aerosol transport through concrete leak paths is important as it governs the environmental source term. In this context, experiments are conducted to study the influence of various parameters like pressure, initial mass concentration, leak path diameter, humidity etc., on the transport and deposition of sodium aerosols in straight leak paths of concrete. The leak paths in concrete specimens are prepared by casting and the diameter of the leak path is measured using thermography technique. Aerosol transport experiments are conducted to measure the transported and plugged aerosol mass in the leak paths and corresponding plugging times. The values of differential pressure, aerosol concentration and relative humidity taken for the study are in the ranges 10–15 kPa, 0.65–3.04 g/m3 and 30–90% respectively. These observations are numerically simulated using 1-Dimensional transport equation. The simulated values are compared with the experimental results and reasonable agreement among them is observed. From the safety assessment view of reactor, the approach presented here is conservative as it is with straight leak paths.
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