Development of a PFM code for evaluating reliability of pressure components subject to transient loading - Shibata, Katsuyuki; Kato, Daisuke; Li, Yinsheng (Nuclear engineering and design, 2001)
Keywords: Applied sciences; Computer simulation; Crack propagation; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; fracture mechanics; Installations for energy generation and conversion: thermal and electrical energy; loading; Mathematical models; Monte Carlo methods; Nuclear energy; pressure vessels; Transients; Nuclear safety; Fracture mechanics; Probabilistic approach; Structure integrity; Computation code; Algorithm; Modeling; Reactor pressure vessel; Light water reactor; Crack propagation; Nuclear reactor