https://server.s4e2.com/crc/tcnpp/index.htmlA comprehensive introduction to the advanced modeling of thermodynamic cycles of nuclear power plants, bridging theory and industrial practice through systemic analysis with Thermoptim.Hugoen-usThu, 22 Jan 2026 14:36:36 +0100https://server.s4e2.com/crc/tcnpp/general/index.htmlThu, 22 Jan 2026 14:36:36 +0100https://server.s4e2.com/crc/tcnpp/general/index.htmlA comprehensive introduction to the advanced modeling of thermodynamic cycles of nuclear power plants, bridging theory and industrial practice through systemic analysis with Thermoptim.https://server.s4e2.com/crc/tcnpp/_toc/index.htmlMon, 01 Jan 0001 00:00:00 +0000https://server.s4e2.com/crc/tcnpp/_toc/index.htmlAdvanced Modeling of Thermodynamic Cycles of Nuclear Power Plants Introduction A Unique Work An Industrial and Strategic Challenge Pedagogical and Methodological Context Systemic and Analytical Modeling Supported by Powerful Methodological Tools Technology Readiness Level Content of the Book Conclusion References 1. Systems Approach and Innovative Teaching of Thermodynamic Cycles of Nuclear Power Plants with Thermoptim 1.1 Analysis of Energy Systems 1.1.1 Introduction to Energy Systems 1.1.2 Illustration: The Steam Power Plant 1.1.3 Functional Structure and Diagram of the Steam Power Plant 1.1.4 Exergy Structure and Diagram of the Steam Power Plant 1.1.5 Complementarity and Duality of Structures 1.2 A New Pedagogical Paradigm for Thermodynamic Cycles of Nuclear Power Plants 1.2.1 Context and Pedagogical Challenges 1.2.2 Limits of Classical Cycle Teaching 1.2.3 An Innovative Pedagogical Approach 1.2.4 A Pedagogy Adapted to Different Audiences 1.2.5 CFRP Approach: An Inductive Progression 1.2.6 Which Equations to Teach? 1.2.7 Comparison with the Anglo-Saxon Approach 1.2.8 Example: Modeling a Steam Turbine 1.3 Thermoptim, a Tool for Modeling and Teaching TCNPPs 1.3.1 Presentation of Thermoptim 1.3.2 Pedagogical Advantages of Thermoptim 1.3.3 Getting Started with Thermoptim 1.4 Conclusion 1.5 References 2. Physical Phenomena Involved in Nuclear Reactors, Panorama of Nuclear Reactors 2.1 Physical Phenomena Involved in Nuclear Reactors 2.1.1 Structure of an Atom 2.1.2 Fission of Uranium 2.1.3 Operating Principles of Nuclear Reactors with Uranium Fission 2.1.4 Conclusion 2.2 Overview of Nuclear Fission Reactors 2.2.1 Introduction 2.2.2 Generations of Nuclear Reactors 2.2.3 Reactor Containment 2.2.4 Pressurized Water Reactors (PWRs) 2.2.5 VVER Reactors 2.2.6 Boiling Water Reactors (BWRs) 2.2.7 RBMK Reactors 2.2.8 Supercritical Water-Cooled Reactors (SCWRs) 2.2.9 Advanced Gas-Cooled Reactors (AGRs) 2.2.10 Pressurized Heavy Water Reactors (PHWRs) or CANDUs 2.2.11 Sodium-Cooled Fast Reactors (SFRs) 2.2.12 Fast Neutron Reactors (FNRs) 2.2.13 Lead-Cooled Fast Reactors (LFRs) 2.2.14 High Temperature Reactors (HTRs) 2.2.15 Very High Temperature Reactors (VHTRs) 2.2.16 Molten Salt Reactors (MSRs) 2.2.17 Fast Molten Salt Reactors (FMSRs) 2.2.18 Relative Sizes of Reactors 2.2.19 Summary 2.2.20 Mind Maps 2.3 Conclusion 2.4 References 3. Steam and Gas Power Cycles: Understanding, Analysis, and Improvement Methodologies 3.1 Introduction to Steam and Gas Power Cycles 3.1.1 Conversion of Heat into Work 3.1.2 Carnot Cycle 3.2 Steam Power Plant and Gas Turbine Cycles 3.2.1 Simple Steam Power Plant 3.2.2 Simple Closed Gas Turbine Cycle 3.3 Comparison with the Carnot Cycle in the Entropy Diagram 3.3.1 Steam Power Plant 3.3.2 Gas Turbine 3.4 Methodological Tools for Analysis and Improvement 3.4.1 Introduction to Thermoptim 3.4.2 Thermoptim Model of the Steam Cycle 3.4.3 Thermoptim Model of the Gas Turbine Cycle 3.4.4 Exergy Balances, Exergy Structures 3.4.5 Process Integration by the Pinch Method 3.5 Conclusion 3.6 References 4. Improvement of Steam Power Cycles 4.1 High-Temperature Steam Power Cycles 4.1.1 Basic Hirn or Rankine Cycle with Superheat 4.1.2 Exergy Balance 4.1.3 Thermodynamic Limits of the Simple Hirn Cycle 4.1.4 Cycle with Reheat 4.1.5 Cycle with Extraction 4.1.6 Technical Constraints in AGRs 4.1.7 SFR, FNR, HTR-PM, MSR, FMSR Cycles 4.2 Supercritical Cycles 4.3 Conclusion 4.4 References 5. Medium Temperature Steam Power Cycles 5.1 Main Categories of Water-Cooled Nuclear Reactors 5.2 Architecture of PWRs 5.3 Architecture of BWRs 5.4 Architecture of RBMK Reactors 5.5 Architecture of CANDU Reactors 5.6 Implications for the Secondary Circuit 5.7 Moisture Separator Reheater 5.8 Expansion in the Wet Steam Region 5.8.1 Reduced Polytropic Efficiency 5.8.2 Increased Mechanical and Chemical Stress on Turbine Blades 5.8.3 Condensate Removal in Turbines 5.8.4 Suboptimal Flow Rates for Feedwater Heating 5.9 Secondary Circuits of Water-Cooled Reactors 5.9.1 Naval Propulsion 5.9.2 Thermodynamic Cycles of Electricity Generation WCRs 5.10 ORC Power Plants 5.11 Binary Cycles 5.12 Conclusion 5.13 References 6. Improvement of Closed Cycle Gas Turbines 6.1 Energy and Exergy Balances of the Simple Cycle 6.1.1 Energy and Exergy Balances of the Simple Cycle 6.1.2 Cycle Improvements 6.2 Supercritical CO₂ Cycles 6.2.1 Characteristics of sCO₂ Cycles 6.2.2 Simple Regeneration Cycle 6.2.3 Pre-Compression Cycle 6.2.4 Recompression Cycle 6.2.5 Partial Cooling Cycle 6.2.6 Conclusion 6.3 Technology Readiness Level of Gas Cycles 6.3.1 TRL of Turbomachinery 6.3.2 TRL of High-Temperature Reactors 6.4 Conclusion 6.5 References 7. Specific Applications and Perspectives: Combined Cycles, Desalination, Hydrogen Production, Cogeneration 7.1 Combined Cycles 7.1.1 General Overview 7.1.2 Single Pressure Combined Cycle 7.1.3 Dual Pressure Level Combined Cycle 7.1.4 Supercritical CO₂ Combined Cycle 7.1.5 Kalina Cycle 7.2 Desalination of Seawater 7.2.1 Boiling Point Elevation 7.2.3 Single Effect Distillation 7.2.4 Multiple Effect Distillation 7.2.5 Multi-Stage Flash Desalination Cycle 7.2.6 Reverse Osmosis Desalination 7.2.7 Mechanical Vapor Compression 7.3 Hydrogen Production, Methane Reforming, Electrolysis 7.3.1 Hydrogen Production Processes 7.3.2 Reforming 7.3.3 Electrolysers 7.4 Cogeneration or Combined Heat and Power (CHP) 7.4.1 Performance Indicators 7.4.2 Boilers and Steam Turbines 7.4.3 Nuclear Cogeneration 7.5 Conclusion 7.6 References 8. Case Studies 8.1 Detailed Model of the AGR 650 MW NPP 8.2 Detailed Model of the NUSCALE 50 MW NPP 8.3 Detailed Model of the NUSCALE 77 MW NPP 8.4 Detailed Model of the ABWR 1350 MW NPP 8.5 Detailed Model of the RBMK 1000 MW NPP 8.6 Detailed Model of the VVER 1000 MW NPP 8.7 Detailed Model of the CANDU 550 MW NPP 8.8 Detailed Model of the Superphenix 1175 MW NPP 8.9 Detailed Model of the HTR-PM 67 MW NPP 8.10 Detailed Model of the Canadian SCWR 1250 MW NPP 8.11 Flamanville 3 EPR Steam Generator Model 8.12 Conclusion 9. Systemic Modeling: A Strategic Imperative for Energy Engineering Education Introduction 9.1 Strategic Value of Thermodynamic Expertise 9.2 An Enduring Professional Asset Appendices Appendix 1 – Reminders A1.1 Thermodynamic Property Diagrams of Pure Substances A1.2 Calculation of Heat Exchangers by the NTU Method A1.3 Conclusion A1.4 References Appendix 2 – Turbines A2.1 Steam Turbines A2.2 Gas Turbines A2.3 Conclusion A2.4 Referenceshttps://server.s4e2.com/crc/tcnpp/chapters/index.htmlThu, 22 Jan 2026 14:35:49 +0100https://server.s4e2.com/crc/tcnpp/chapters/index.htmlIntroduction This book introduces an innovative pedagogical and methodological approach to modeling and analyzing energy systems using the Thermoptim simulator. It replaces heavy mathematical formalism with graphical modeling and interactive simulation, allowing learners to focus on understanding technologies and system architectures. Designed for both beginners and advanced users, it bridges theory and practice by providing a unified framework for studying real-world energy conversion technologies. The book combines fundamental thermodynamics, component modeling, and system optimization within a constructivist learning environment that promotes autonomy, realism, and critical analysis.https://server.s4e2.com/crc/tcnpp/resources/index.htmlThu, 22 Jan 2026 14:35:49 +0100https://server.s4e2.com/crc/tcnpp/resources/index.htmlResources In this section, you will find resources presented in a way that complements those available chapter by chapter.https://server.s4e2.com/crc/tcnpp/nuscle/index.htmlThu, 22 Jan 2026 14:35:10 +0100https://server.s4e2.com/crc/tcnpp/nuscle/index.htmlNUSCLE – A Simplified Model of the Thermodynamic Cycle of a Water-Cooled Nuclear Power Plant General Introduction This document introduces NUSCLE (Nuclear Secondary Circuit Lite Emulator), a simplified model of the thermodynamic cycle of a Water-Cooled Reactor (WCR) nuclear power plant—such as PWRs, BWRs, RBMKs, or CANDUs. NUSCLE is designed to simulate part-load operation. It includes only four steam extractions and five turbine stage groups, compared to, for instance, eleven and nine respectively in the EPR Flamanville 3 cycle.