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Study of Siphon Breaker Experiment and Simulation for a Research Reactor
Published on: September 26, 2017
Numerical simulation for the control rod assembly drop time evaluation in a LFR.
Emmanuel Maurice Arthur1,2,3, Chaodong Zhang1, Seth Kofi Debrah2,3
1Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031, China.
Computational Fluid Dynamics (CFD) simulations reveal lead-based reactor Control Rod Assembly (CRA) drop dynamics. High lead-bismuth eutectic (LBE) density and CRA mass significantly influence drop time, crucial for safety system design.
Area of Science:
- Nuclear Engineering
- Computational Fluid Dynamics (CFD)
- Reactor Safety
Background:
- Scram events require rapid Control Rod Assembly (CRA) insertion to shut down nuclear reactors.
- Accurate simulation of CRA dynamics is essential for ensuring reactor safety and optimizing design.
Purpose of the Study:
- To investigate the dynamics of Control Rod Assembly (CRA) drop in a lead-based research reactor using Computational Fluid Dynamics (CFD).
- To analyze the influence of fluid properties and CRA mass on the drop time during scram events.
Main Methods:
- Development of a 3D CFD model for the CRA within a lead-bismuth eutectic (LBE) filled guide tube.
- Application of averaged Navier-Stokes equations coupled with a dynamic mesh and a rigid body Fluid-Structure Interaction (FSI) method.
- Validation of the CFD model against existing literature data.
Main Results:
- The CFD model demonstrated applicability and reliability in simulating CRA drop dynamics.
- Lead-bismuth eutectic (LBE) coolant's high density was identified as the primary factor affecting CRA drop time.
- Increased CRA mass was found to reduce drop time due to enhanced driving force.
Conclusions:
- The employed CFD methodology provides a reliable approach for predicting CRA drop parameters.
- Findings offer valuable reference data for the design and modification of CRA and their drive mechanisms for enhanced reactor safety.
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