Join thousands of book lovers
Sign up to our newsletter and receive discounts and inspiration for your next reading experience.
By signing up, you agree to our Privacy Policy.You can, at any time, unsubscribe from our newsletters.
In using risk-informed approaches for ensuring safety of operating nuclear power plants (NPPs), risk importance measures obtained from probabilistic risk assessments (PRAs) of the plants are integral elements of consideration in many cases. Obtaining these measures in appropriate forms is helpful for decision makers and can facilitate the use of risk information.
Addresses a few issues essential for achieving a consistent Design-By-Analysis in accordance with the ASME Boiler & Pressure Vessel Code: nonlinear alternative rules, fatigue, thermal ratcheting, dynamic loads, strain-based criteria, nonlinear finite element procedures, supports under combined stresses, and others.
Sign up to our newsletter and receive discounts and inspiration for your next reading experience.
By signing up, you agree to our Privacy Policy.