References
- W. MA et al., “Study on the Load Loss Characteristics of a Space Nuclear Power System with Multi Brayton Loops,” Ann. Nucl. Energy, 185, 109702 (2023); http://dx.doi.org/10.1016/j.anucene.2023.109702.
- G. BLACK et al., “Prospects for Nuclear Microreactors: A Review of the Technology, Economics, and Regulatory Considerations,” Nucl. Technol., 209, S1–S20 (2023); http://dx.doi.org/10.1080/00295450.2022.2118626.
- D. SHROPSHIRE, G. BLACK, and K. ARAUJO, “Global Market Analysis of Microreactors,” INL/EXT-21-63214-Rev000, Idaho National Laboratory (2021); http://dx.doi.org/10.2172/1806274.
- J. KENNEDY et al., “Special Purpose Application Reactors: Systems Integration Decision Support,” INL/EXT-18-51369-Rev001, Idaho National Laboratory (2018); http://dx.doi.org/10.2172/1475413.
- “Advances in Small Modular Reactor Technology Developments, A Supplement to: IAEA Advanced Reactors Information System (ARIS),” International Atomic Energy Agency (2020).
- K. KUGELER and Z. ZHANG, Modular High-Temperature Gas-Cooled Reactor Power Plant, Springer Berlin Heidelberg (2019); http://dx.doi.org/10.1007/978-3-662-57712-7.
- J. WANG and Y. GU, “Parametric Studies on Different Gas Turbine Cycles for a High Temperature Gas-Cooled Reactor,” Nucl. Eng. Des., 235, 1761 (2005); http://dx.doi.org/10.1016/j.nucengdes.2005.02.007.
- P. G. ROUSSEAU and G. P. GREYVENSTEIN, “One-Dimensional Reactor Model for the Integrated Simulation of the PBMR Power Plant” (2005).
- M. M. TILLER, MODELICA–Introduction to Physical Modeling with Modelica, Kluwer Academic Publishers (2001).
- P. FRITZSON, Principles of Object-Oriented Modeling and Simulation with Modelica 3.3: A Cyber-Physical Approach, John Wiley & Sons (2014).
- C. FAZEKAS, G. SZEDERKÉNYI, and K. M. HANGOS, “A Simple Dynamic Model of the Primary Circuit in VVER Plants for Controller Design Purposes,” Nucl. Eng. Des., 237, 1071 (2007); http://dx.doi.org/10.1016/j.nucengdes.2006.12.002.
- P. FRITZSON and V. ENGELSON, “Modelica—A Unified Object-Oriented Language for System Modeling and Simulation,” ECOOP’98—Object-Oriented Programming, Lecture Notes in Computer Science, pp. 67–90, E. JUL, Ed., Springer Berlin Heidelberg (1998); http://dx.doi.org/10.1007/BFb0054087.
- P. FRITZSON et al., “The OpenModelica Integrated Environment for Modeling, Simulation, and Model-Based Development,” MIC J., 41, 241 (2020); http://dx.doi.org/10.4173/mic.2020.4.1.
- Z. GAO and L. SHI, “Thermal Hydraulic Calculation of the HTR-10 for the Initial and Equilibrium Core,” Nucl. Eng. Des., 218, 51 (2002); http://dx.doi.org/10.1016/S0029-5493(02)00198-X.
- E. C. VERKERK, Dynamics of the Pebble-Bed Nuclear Reactor in the Direct Brayton Cycle[D], Delft University of Technology, The Netherlands (2000).
- “Thermal Hydraulics Design Report of the 10 MW High Temperature Gas Cooled Reactor,” Tsinghua University, Institute of Nuclear Energy Technology (2001) (in Chinese).
- Z. SUN, Reactor Thermohydraulics, Harbin Engineering University Press, Harbin (2017) (In Chinese).
- X. L. YAN, “Dynamic Analysis and Control System Design for an Advanced Nuclear Gas Turbine Power Plant,” PhD Thesis, Massachusetts Institute of Technology (May 1990).
- H. ZHANG and D. ZHOU, Thermal System Modeling and Simulation Technology, Shanghai Jiao Tong University Press, Shanghai (2018) (in Chinese).
- H. XIE, G. ZHAO, and J. WANG, “Analysis of Startup Parameters for Direct Helium Turbine Cycle System of High Temperature Gas-Cooled Reactor,” At. Energy Sci. Technol., 42, 1018 (2008).
- V. GNIELINSKI, “New Equations for Heat and Mass Transfer in Turbulent Pipe and Channel Flow,” Int. Chem. Eng., 16, 359 (1976).
- L. TANG, “Modeling and Simulation of Gas Turbine Systems,” MD Thesis, Chongqing University (2008).
- L. WENLONG et al., “Development and Primary Verification of a Transient Analysis Software for High Temperature Gas-Cooled Reactor Helium Turbine Power System,” Nucl. Eng. Des., 250, 219 (2012); http://dx.doi.org/10.1016/j.nucengdes.2012.05.007.