Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module
Author | : Adrian Leandro |
Publisher | : |
Total Pages | : |
Release | : 2018 |
ISBN-10 | : OCLC:1050770825 |
ISBN-13 | : |
Rating | : 4/5 (25 Downloads) |
Book excerpt: System analysis codes have a long history of providing best-estimate and conservative safety analysis for both light water and advanced reactor technologies. As interest continues to expand with advanced reactor concepts, system analysis codes will need revisions to accommodate the behavior of these technologies. The codes will also need to be updated to the latest numerical techniques to shorten execution time and increase the accuracy of results. One such tool that already encompasses these techniques is the System Analysis Module (SAM). An advanced reactor concept with recent interest is the Molten Salt Reactor (MSR). This concept is built upon the Molten Salt Reactor Experiment (MSRE), which provided early data and experience. Therefore, the objective of this work is to use legacy MSRE data as a basis of comparison with SAM results.Two MSRE models are developed to evaluate SAM. One model is the SAM MSRE water mockup where experimental data was collected for pressure drop measurements. The other model is the complete MSRE primary loop. The MSRE system model incorporates fluoride salt fuel/coolant with heat transfer in both the core and heat exchanger. Estimates for the core coolant temperature profiles allow this reactor to be evaluated. The primary loop model is also altered for various additional studies, such as simulating varying coolant properties and a loss of flow (LOF) response.The SAM model results for the pressure drop of the water mockup model are within 6% with measurements, which provides confidence that the models geometry is physically accurate over a range of flow rates. Coolant temperatures are also accurate for the primary loop model matching the expected axial change in temperature. Alternative coolant properties from the literature with different actinide content yield similar trends in core temperature profiles. A thermal hydraulic demonstration of a LOF transient shows the importance of coupling SAM thermal hydraulic analysis to neutronics. This coupling is essential for simulating MSR transients with system analysis codes.