Nuclear Reactor Thermal-Hydraulics : Past, Present and Future

Title: Nuclear Reactor Thermal-Hydraulics : Past, Present and Future
Author: Pradip Saha
ISBN: 0791861287 / 9780791861288
Format: Hard Cover
Pages: 152
Publisher: ASME
Year: 2017
Availability: 45-60 days

Tab Article

This monograph summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for the water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation IV reactors.

This includes discussion on the steady-state reactor thermal hydraulics including subchannel analysis, evolution of emergency core cooling systems (ECCS) from active to fully passive systems to remove the decay heat, and development and consolidation of the best-estimate safety analysis methodology. With substantial increase in computing power, the computational fluid dynamics (CFD) tools for single-phase and multi-phase flows are being used more these days to address some of the important reactor thermal-hydraulics phenomena which could not be analyzed earlier using the traditional one-dimensional or coarse three-dimensional analysis tools. Development of multi-physics methodology encompassing neutronics, thermal-hydraulics, thermal-mechanical and coolant chemistry has also started.

Tab Article

Series Editors Preface
Abstract
Acknowledgements

Chapter 1 : Introduction
Chapter 2 : Steady State Reactor Thermal-Hydraulics
Chapter 3 : Nuclear Reactor Safety Systems
Chapter 4 : Nuclear Reactor Safety Analysis
Chapter 5 : Summary and Conclusions

References
Author Biography
Index