Numerical simulation of complex hexagonal structures to predict drop behavior under submerged and fluid flow condition

This study simulated a control rod assembly (CRA), which is a part of reactor shutdown systems, in immersed and fluid flow conditions. The CRA was inserted into the reactor core within a predetermined time limit under normal and abnormal operating conditions, and the CRA (which consists of complex geometric shapes) drop behavior is numerically modeled for simulation. | Numerical simulation of complex hexagonal structures to predict drop behavior under submerged and fluid flow condition Nuclear Engineering and Technology 51 (2019) 31e44 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article Numerical simulation of complex hexagonal structures to predict drop behavior under submerged and fluid flow conditions . Yoon a, *, . Lee a, . Oh b, . Choi b a Korea Atomic Energy Research Institute, Daedeokdaero 989 Beongil-111, Daejeon, South Korea b ELSOLTEC Inc., Heungdeokjoongangro 120, Yongin, South Korea a r t i c l e i n f o a b s t r a c t Article history: This study simulated a control rod assembly (CRA), which is a part of reactor shutdown systems, in Received 20 April 2018 immersed and fluid flow conditions. The CRA was inserted into the reactor core within a predetermined Received in revised form time limit under normal and abnormal operating conditions, and the CRA (which consists of complex 14 August 2018 geometric shapes) drop behavior is numerically modeled for simulation. A full-scale prototype CRA drop Accepted 17 August 2018 Available online 28 August 2018 test is established under room temperature and water-fluid conditions for verification and validation. This paper describes the details of the numerical modeling and analysis results of the several conditions. Results from the developed numerical simulation code are compared with the test results to verify the Keywords: Fluid-structure interaction numerical model and developed computer code. The developed code is in very good agreement with the Hexagonal structures test results and this numerical analysis model and method may replace the experimental and CFD Immersed and fluid flow condition method to predict the drop behavior of CRA. Control rod © 2018 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an .

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