Description
This handbook is supported by the Materials Ageing Institute (MAI) and Électricité de France (EDF) and is an extensive update to the previous edition, featuring up-to-minute information to reflect the state of the art as of 2020. Since its founding in 2008, the MAI has succeeded in expanding its membership and today represents two-thirds of the world's installed nuclear power capacity, benefiting from nearly 5,000 years of combined experience in reactor operation. The vast archive of past observational data and world-leading expert recommendations presented in this handbook leverage the unique expertise of the MAI in studying the key degradation phenomena of materials to ensure the secure and sustainable operation of carbon-free electricity production. It is a must-have on the desks of any engineers or researchers involved in ageing management for light-water reactors.
Author: François Cattant
Publisher: Springer
Published: 11/10/2021
Pages: 2150
Binding Type: Hardcover
Weight: 12.75lbs
Size: 9.50h x 6.50w x 6.00d
ISBN13: 9783030855994
ISBN10: 3030855996
BISAC Categories:
- Technology & Engineering | Materials Science | Thin Films, Surfaces & Interfaces
- Technology & Engineering | Power Resources | Nuclear
- Science | Chemistry | Inorganic
About the Author
François Cattant graduated in chemical engineering in 1974 and joined Electricity of France (EDF) in 1975 as a chemical engineer in the Plant Operation Division working on the water and steam conditioning of power plants. Two years later, he moved to the hot laboratory at the Chinon Nuclear Power Plant to examine failures and do root cause analysis of gas-cooled reactor components, including fuel. In 1980, he became the manager of a regional section for water and steam chemistry, chemical cleaning and non-destructive examination in fossil stations. He returned to the Chinon hot laboratory 3 years later where he continued to focus on failure root cause analysis of irradiated or contaminated components, monitoring of reactor pressure vessel (RPV) irradiation programs, examination of steam generator tubes, RPV head penetrations, split pins, pressurizer nozzles, valves, reactor cooling system cast elbows, piping, fuel bundle and rods, rod cluster control assemblies, and much more.
During 1995-1998, he was assigned as an expatriate engineer to the Nuclear Maintenance Applications Center of the Electric Power Research Institute in the USA where he worked on nuclear plant maintenance issues. While at EPRI, he also participated as an outside expert on the examination of Ringhals 3 retired steam generator.