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UID:pretalx-amfc2026-QDN8AR@modelica.simtek.cc
DTSTART;TZID=CST:20260920T130000
DTEND;TZID=CST:20260920T150000
DESCRIPTION:This tutorial provides a comprehensive overview of the OpenMode
 lica architecture and development environment. It covers the basics of the
  Modelica language\, OMEdit GUI operations\, and model compilation princip
 les. The hands-on session will guide beginners through component library u
 sage and drag-and-drop modeling to complete a full workflow from environme
 nt setup to simulation execution.
DTSTAMP:20261004T070733Z
LOCATION:Modelica Technology & AI (R1001)
SUMMARY:Workshop 2: OpenModelica Introduction and Hands-on Practice - Cuiti
 ng Peng
URL:https://modelica.simtek.cc/amfc2026/talk/QDN8AR/
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UID:pretalx-amfc2026-FWVNUG@modelica.simtek.cc
DTSTART;TZID=CST:20260921T120500
DTEND;TZID=CST:20260921T123000
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:20261004T070733Z
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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UID:pretalx-amfc2026-9DQNQJ@modelica.simtek.cc
DTSTART;TZID=CST:20260922T115500
DTEND;TZID=CST:20260922T122000
DESCRIPTION:Nuclear power systems are complex multi-disciplinary systems in
 volving thermal hydraulics\, fluid mechanics\, control engineering and ele
 ctrical engineering. Comprehensive performance analysis and optimization o
 f such systems require coupled multi-disciplinary modeling and simulation.
  Nevertheless\, co-simulation via interfaces between separate single-disci
 pline simulation software brings numerous inherent drawbacks. Hualong One 
 is China’s domestically developed third-generation pressurized water rea
 ctor. To accelerate system modeling and simulation efficiency\, this paper
  independently develops the unified multi-disciplinary modeling library CG
 N_HPR V1.0 based on Modelica and the hierarchical modeling method\, with t
 he domestic MWorks simulation platform as the core development environment
 . Adopting a four-tier architecture consisting of basic\, component\, equi
 pment and system levels\, the library supports modular\, parameterized and
  visual modeling for streamlined simulation analysis\, and addresses the t
 echnical bottleneck of insufficient deep coupling in traditional multi-dis
 ciplinary simulation workflows. Typical operating conditions of Hualong On
 e are modeled and simulated using the proposed library\, which preliminari
 ly verifies the validity of the Modelica-based system simulation model. Th
 e results demonstrate that the Modelica-enabled simulation framework enabl
 es seamless integration of cross-disciplinary subsystems\, mitigates the d
 ifficulties in multi-disciplinary coupled simulation for nuclear power pla
 nts\, and improves overall system analysis and design capacity\, providing
  key technical support for unit safety assessment and operational optimiza
 tion.
DTSTAMP:20261004T070733Z
LOCATION:FMI & MBSE (R2001)
SUMMARY:Research on Multi-disciplinary Unified Modeling and Simulation Tech
 nology of Hualong One System - Cuiting Peng\, Fuhong Luo\, Hong Lv
URL:https://modelica.simtek.cc/amfc2026/talk/9DQNQJ/
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