Abstract
In recent years, there has been renewed interest in Molten Salter Reactors (MSRs) for their potential advantages compared to reactors that rely on solid fuel. In response to such interest, the System Analysis Module (SAM) was enhanced to include MSR-specific modeling features including a delayed neutron precursor drift model and a modified point kinetics model. This paper discusses the validation of these features using the experiments conducted in the Molten Salt Reactor Experiment (MSRE). These experiments include the pump start-up and coast-down tests at zero power and a thermal convection test. For the zero power tests, the change in pump speeds induces flow rate changes in the core that impact the precursor concentrations. This introduces a neutron imbalance and requires the adjustment of the control rods to counter-balance this effect. SAM was used to evaluate the precursor concentration in the core as a function of time, and the resulting changes in reactivity were evaluated through the modified point kinetics equation. The results show good agreement with the experimental data. It should be noted that the pump performance curve used in this analysis was re-constructed based on the initial water test data of the fuel pump. The steady-state pump curve is assumed to be applicable to transient flow operations. The thermal convection test was conducted by shutting off the pumps, reducing the inlet core temperature for 360 minutes, and allowing the power to be adjusted by the inherent feedbacks of the system. The power level during this transient was evaluated by SAM as a function of time.
Highlights
One of the objectives of the Nuclear Energy Advanced Modeling and Simulation program within the U.S DOE Office of Nuclear Energy (DOE-NE) is to develop modeling and simulation capabilities to predict the performance and safety behavior of a range of different nuclear reactor types
The focus of this paper is on the application of one of these tools, the System Analysis Module (SAM) [1], to reproduce measured data from a set of time-dependent experiments conducted on the Molten Salt Reactor Experiment (MSRE)
Experiments conducted in the MSRE program [7,8] were reviewed, and three experiments were selected to validate these Molten Salter Reactors (MSRs) modeling capabilities in SAM
Summary
One of the objectives of the Nuclear Energy Advanced Modeling and Simulation program within the U.S DOE Office of Nuclear Energy (DOE-NE) is to develop modeling and simulation capabilities to predict the performance and safety behavior of a range of different nuclear reactor types. Given the goal of having reactor developers and regulators use this code to predict safety performance for design and licensing purposes, it is important to demonstrate that these two new features implemented in SAM are able to predict transients of MSR systems correctly. For this purpose, experiments conducted in the MSRE program [7,8] were reviewed, and three experiments were selected to validate these MSR modeling capabilities in SAM. The pure thermal hydraulic validation using the MSRE water mockup test data and preliminary thermal hydraulic analysis of MSRE during normal operating condition and a postulated loss-of-flow transient were performed in an earlier study [9] using the SAM code
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