The IAEA facilitated the co-operation on research and development, including the development and validation of computer codes for design and safety analysis of NPPs, to bring together the experts from the Member States with water cooled reactor technologies experienced in developing and using the severe accident codes to further advance the state-of-knowledge on uncertainty propagation in severe accident simulation and modelling analyses, as well as increase the sophistication and competency of the practitioners in this field. This publication is one out of five in the TECDOC Series addressing specific reactor lines and it provides descriptions by contributing institutions of their utilized uncertainty and sensitivity methods for severe accidents analysis in large Pressurized Water Reactors (PWRs) and in Integral PWR-type Small Modular Reactors. This publication is intended for nuclear engineers, vendors, researchers, code developers, university professors and university students, regulatory experts, and nuclear power plant designers and planners.
Advancing the State of the Practice, Uncertainty, Sensitivity Methodologies, Severe Accident Analysis, Water Cooled Reactors, Large Pressurized Water Reactors, PWR, Small Modular Reactor, SMR Types, Safety Measures, Nuclear Reactor Accidents, Specific Reactor Lines, Integral PWR-Type Small Modular Reactor, Calculations, Benchmark Results, Sensitivity Analyses, PWR and SMR Applications, Analysis Scope, Framework, Severe Accident Codes, Contribution of the Member States, Validation of Computer Codes, Design and Safety Analysis of NPPs, State-of-Knowledge, Uncertainty Propagation, Severe Accident Simulation, MELCOR Code, MAAP Code, ATHLET Code, RELAP/SCDAPSIM Code, SCALE and NESTLE Codes, 3KEYMASTER Code, COOLAP Code, Coordinated Research Project, CRP, Nuclear Engineers, Vendors, Code Developers, Regulatory Experts, Review
