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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:20261004T070622Z
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-BDKE8N@modelica.simtek.cc
DTSTART;TZID=CST:20260921T135000
DTEND;TZID=CST:20260921T141500
DESCRIPTION:While Modelica has become a standard for multi-domain modeling 
 in various complex engineering fields\, professional and systematic model 
 libraries specifically tailored for the nuclear power sector remain scarce
 . To bridge this gap\, this paper presents the development of a specialize
 d Modelica fluid component library for Small Modular Reactor (SMR) systems
 . Serving as a critical module within the broader CGN_NHR library\, this f
 ramework bridges the gap between fundamental fluid mechanisms\, equipment-
 level modeling\, and system-level assembly. We detail the library’s arch
 itecture\, design philosophy\, and the mathematical formulation of its cor
 e components. To verify its validity and reliability\, a systemlevel model
  was constructed and benchmarked against the industry-standard RELAP5 mode
 l. Comparative results confirm that the proposed library offers high effic
 iency and accuracy\, establishing a robust technical foundation for the ra
 pid design\, simulation\, and verification of nuclear power systems.
DTSTAMP:20261004T070622Z
LOCATION:Energy (R2002)
SUMMARY:A Modelica-based Fluid Library for Small Modular Reactors: Design a
 nd Verification - Sixin Liu\, Hao Hong\, Hong Lv
URL:https://modelica.simtek.cc/amfc2026/talk/BDKE8N/
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UID:pretalx-amfc2026-BGZSJF@modelica.simtek.cc
DTSTART;TZID=CST:20260921T141500
DTEND;TZID=CST:20260921T144000
DESCRIPTION:As the pivotal equipment connecting the primary and secondary l
 oops of pressurized water reactor nuclear power plants\, the dynamic therm
 o-hydraulic characteristics of the nuclear steam generator are directly re
 lated to the safe and stable operation of the unit. However\, traditional 
 modeling approaches suffer from poor versatility and low efficiency\, maki
 ng it difficult to meet the R&D demands for diverse application scenarios 
 and iterative optimization. Addressing these bottlenecks\, this paper prop
 oses a modular modeling and dynamic simulation method for nuclear steam ge
 nerators based on the Modelica language. First\, based on a hierarchical m
 odeling approach\, component-level models covering plena\, pipes\, heat st
 ructures\, steam-water separators\, and feedwater plena are constructed to
  achieve free configuration and visual simulation modeling. Second\, accor
 ding to the operating principles and structure of the nuclear steam genera
 tor\, a complete dynamic simulation model is assembled using these compone
 nt-level models. Finally\, the established model is validated against the 
 RELAP5 code to verify the effectiveness and reliability of the proposed me
 thod. The results indicate that the Modelica-based steam generator simulat
 ion model combines high accuracy with high efficiency\, providing signific
 ant technical support for the rapid design and verification of nuclear pow
 er systems.
DTSTAMP:20261004T070622Z
LOCATION:Energy (R2002)
SUMMARY:Research on Dynamic Simulation of Nuclear Power Steam Generator Bas
 ed on Modelica - Hao Hong\, Sixin Liu\, Hong Lv
URL:https://modelica.simtek.cc/amfc2026/talk/BGZSJF/
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