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November 30–December 3, 2021
Washington, DC|Washington Hilton
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Helping to save the plant safety puzzle: An overview of PRA
Probabilistic risk assessments (PRAs) have advanced the safe operation of the U.S. reactor fleet over many decades. Risk insights from PRAs have provided information from many different perspectives, from what is most important to maintain at a facility to a better understanding of how to address new information regarding safety issues. The methods and tools that have supported the creation and enhancement of PRA models were established through multiple decades of research, starting with WASH-1400, The Reactor Safety Study,1 published in 1975, through the comprehensive plant-specific models in use today.
V. G. Kritsky
Item ID: 690053|ISBN: 978-0-89448-565-7
1995|1st Edition|313 pages
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This book addresses structural material corrosion in coolant circuits, simulation of erosion corrosion of carbon and low-alloy steels, and simulation of stress corrosion. It also discusses corrosion of copper alloys, zirconium corrosion, optimization of water chemistry at operating nuclear power plants, coolant tendency to deposit hardness salts on heat-transfer surfaces, and inspection of metallic components. In addition, there are two appendixes, the first showing the chemical composition of steels, the second discussing solubility of iron, cobalt, zinc, and copper corrosion products under conditions simulating power unit water chemistry.