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This book is indexed in
Engineering » Energy Engineering
Nuclear Power - System Simulations and Operation
Edited by Pavel Tsvetkov, ISBN 978-953-307-506-8, Hard cover, 192 pages, Publisher: InTech, Chapters published September 06, 2011 under CC BY-NC-SA 3.0 license
DOI: 10.5772/986
At the onset of the 21st century, we are searching for reliable and sustainable energy sources that have a potential to support growing economies developing at accelerated growth rates, technology advances improving quality of life and becoming available to larger and larger populations. The quest for robust sustainable energy supplies meeting the above constraints leads us to the nuclear power technology. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. Catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, requirements and facilitated growing interests in designs, which can withstand natural disasters and avoid catastrophic consequences. This book is one in a series of books on nuclear power published by InTech. It consists of ten chapters on system simulations and operational aspects. Our book does not aim at a complete coverage or a broad range. Instead, the included chapters shine light at existing challenges, solutions and approaches. Authors hope to share ideas and findings so that new ideas and directions can potentially be developed focusing on operational characteristics of nuclear power plants. The consistent thread throughout all chapters is the "system-thinking" approach synthesizing provided information and ideas. The book targets everyone with interests in system simulations and nuclear power operational aspects as its potential readership groups - students, researchers and practitioners.
- Chapter 1
Simulation and Simulators for Nuclear Power Generation - Chapter 2
Safety Studies and General Simulations of Research Reactors Using Nuclear Codes - Chapter 3
Development of an Appendix K Version of RELAP5-3D and Associated Deterministic-Realistic Hybrid Methodology for LOCA Licensing Analysis - Chapter 4
Analysis of Error Propagation Between Software Processes - Chapter 5
Thermal-Hydraulic Analysis in Support of Plant Operation - Chapter 6
A Literature Survey of Neutronics and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters; Artificial Neural Networks as the VVER-1000 Core Predictor - Chapter 7
Recent Trends in Mathematical Modeling and Simulation of Fission Product Transport From Fuel to Primary Coolant of PWRs - Chapter 8
Thermal-Hydraulic Simulation of Supercritical-Water-Cooled Reactors - Chapter 9
Non-Linear Design Evaluation of Class 1-3 Nuclear Power Piping - Chapter 10
The Text-Mining Approach Towards Risk Communication in Environmental Science
