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UID:pretalx-amfc2026-FWVNUG@modelica.simtek.cc
DTSTART;TZID=CST:20260921T120500
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DESCRIPTION:In this application\, based on the CGN_NHR1.0 model library\, a
 n overall simulation model of the intermediate loop of the low-temperature
  heating reactor was built using a visual drag-and-drop modeling method. T
 he multi-domain coupling and collaborative simulation\nverification were c
 arried out using the MBSE method. The typical working condition selected w
 as the step reduction of rated full power (100% FP) to 70% FP load disturb
 ance. Oriented by the SysML functional requirements\, a joint simulation f
 ramework for reactor physics\, thermal-hydraulic\, and control systems was
  constructed. The simulation conditions were divided into two stages: the 
 first 100 seconds of the system maintained a steady state operation\, and 
 at the 100-second moment\, a 70% FP step load reduction disturbance was ap
 plied. The simulation results showed that the various thermal-hydraulic pa
 rameters of the intermediate loop could return to stability within 450 sec
 onds after the disturbance occurred\, and the dynamic response performance
  of the system control was better than the design-expected indicators. Res
 earch has confirmed that the SysML-Modelica joint modeling approach is app
 licable to the design and analysis of complex nuclear energy systems. The 
 "requirement driven - functional mapping - dynamic verification" closed-lo
 op verification mode constructed in this study can provide reliable theore
 tical and methodological support for the digital design and development of
  nuclear energy equipment.
DTSTAMP:20261004T070648Z
LOCATION:Energy (R2002)
SUMMARY:Application of MBSE in the Design of a Small Modular Reactor Interm
 ediate Circuit System - Mingliang Chen\, Cuiting Peng\, Sixin Liu
URL:https://modelica.simtek.cc/amfc2026/talk/FWVNUG/
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