کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
296158 511712 2015 13 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
A dynamic model of a passively cooled small modular reactor for controller design purposes
ترجمه فارسی عنوان
یک مدل پویا از یک راکتور مدولار کوچک منفعل خنک برای اهداف طراحی کنترل کننده
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی


• A mathematical dynamic model is developed for a passively cooled small modular reactor.
• Reactor response associated single-phase natural circulation is analyzed.
• A moving boundary model for a helical-coil steam generator is analyzed.
• Dynamic responses of the overall model to representative perturbations are evaluated.
• This compact model can be utilized for control system design.

An analytical dynamic model for a passively cooled small modular reactor (SMR) is developed using a state-variable lumped parameter approach. Reactor power is represented by the generation time formulation of the point kinetics equations with a single combined neutron precursor group. The heat transfer process in the core is described via an overall heat transfer coefficient by defining two coolant lumps paired to a single fuel lump. In addition, a thermal–hydraulics model for single-phase natural circulation is incorporated. For the helical-coil steam generator, a moving-boundary model including subcooled, two-phase, and superheated regions is utilized. Finally, the hot leg riser and downcomer regions are expressed by first-order lags. The performance of the overall system described by ordinary differential equations (ODEs) is evaluated by the Simulink dynamic environment and directly using a MATLAB ODE solver recommended for stiff systems. Simulation results based on NuScale SMR design data show that the initial steady-state values for 100% power are within range of the design data and the model can predict the system dynamics due to typical perturbations, e.g., control rod movement and change in feedwater mass flow rate and temperature. The model developed in this work can be utilized as a foundation for designing and testing a suitable control algorithm for reactor thermal power.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 289, August 2015, Pages 218–230
نویسندگان
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