<?xml version="1.0" encoding="utf-8" standalone="yes"?><rss version="2.0" xmlns:atom="http://www.w3.org/2005/Atom"><channel><title>Chapter 8 :: TCNPP</title><link>https://server.s4e2.com/crc/tcnpp/chapters/chapter8/index.html</link><description>📊 Chapter 8: Case Studies 11 Real-World Case Studies Modeled with Thermoptim
Plant Reactor Type Power (MWe) Efficiency Key Features AGR Graphite-gas 650 41% 8 feedwater heaters, MSR NuScale (SMR) PWR 50/77 ~30% Natural circulation, passive safety Flamanville 3 (EPR) PWR 1650 36% 5 extractions, MSR Superphénix Fast (Na-cooled) 1174 40% Highly superheated steam (487°C) HTR-PM High-temperature (He) 210 33.76% Helium cycle, cogeneration potential Canadian SCWR Supercritical water - 48.73% Gen IV technology Detailed Analyses:</description><generator>Hugo</generator><language>en-us</language><lastBuildDate>Thu, 22 Jan 2026 14:36:36 +0100</lastBuildDate><atom:link href="https://server.s4e2.com/crc/tcnpp/chapters/chapter8/index.xml" rel="self" type="application/rss+xml"/><item><title>Table of Contents</title><link>https://server.s4e2.com/crc/tcnpp/chapters/chapter8/_toc/index.html</link><pubDate>Thu, 22 Jan 2026 14:35:10 +0100</pubDate><guid>https://server.s4e2.com/crc/tcnpp/chapters/chapter8/_toc/index.html</guid><description>Table of Contents — Volume 2 Advanced Modeling of Thermodynamic Cycles of Nuclear Power Plants
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</description></item><item><title>Resources</title><link>https://server.s4e2.com/crc/tcnpp/chapters/chapter8/_resources/index.html</link><pubDate>Thu, 22 Jan 2026 14:36:36 +0100</pubDate><guid>https://server.s4e2.com/crc/tcnpp/chapters/chapter8/_resources/index.html</guid><description>Resources 📘 Chapter 8: Detailed Flowsheets of Nuclear Power Plant Cycles Complementary Resources and SVG Flowsheets
⚠️ Important Notes About These Resources The resources on this page complement the content of Chapter 8 in Advanced Modeling of Thermodynamic Cycles of Nuclear Power Plants.
The flowsheets below are SVG diagrams accessible directly in a browser. Most reactor types are provided in two layouts: horizontal (full-width view) and stacked (compact view). 8.1 — AGR Hartlepool · 625 MWe United Kingdom · Gas-cooled · Graphite moderated · CO₂ · British design</description></item></channel></rss>