Risk-Informed design process of the IRIS reactor [PDF]
Westinghouse is currently conducting the pre-application licensing of the International Reactor Innovative and Secure (IRIS). The design philosophy of the IRIS has been based on the concept of Safety-by-DesignTM and within this framework the PSA is ...
A. MAIOLI +5 more
core
An Interpretable Time Series Data Prediction Framework for Severe Accidents in Nuclear Power Plants. [PDF]
Fu Y, Zhang D, Xiao Y, Wang Z, Zhou H.
europepmc +1 more source
An open time-series simulated dataset covering various accidents for nuclear power plants. [PDF]
Qi B +5 more
europepmc +1 more source
A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next. [PDF]
Huang Q +6 more
europepmc +1 more source
Application target image of a small modular fluoride salt-cooled high temperature reactor based on the analysis of energy demand and environmental conditions in western China. [PDF]
Guo Y, Dai Y, Zhang J, Jiang D, Fu Y.
europepmc +1 more source
Analysis of a space emergency ammonia dump using the FLOW-NET two-phase flow program [PDF]
Venting of cryogenic and non-cryogenic fluids to a vacuum or a very low pressure will take place in many space-based systems that are currently being designed.
Navickas, J., Rivard, W. C.
core +1 more source
Preparación de un manual de usuario para la realización de análisis de seguridad mediante RELAP [PDF]
El objetivo principal del presente proyecto es mejorar las condiciones de trabajo y aprendizaje de los usuarios en el uso del código termohidráulico RELAP en lo relativo a la realización de análisis de seguridad.
Casamor Vidal, Max
core
RELAP5/MOD3.3 Code Validation with Plant Abnormal Event
Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event which occurred at Krško Nuclear Power Plant (NPP) on ...
Andrej Prošek, Borut Mavko
doaj +1 more source
RELAP5 simulation of two-phase flow experiments in vertical helical tubes [PDF]
In the framework of the studies concerning the thermalfluid dynamic phenomena in helicoidal pipes of the innovative nuclear reactor IRIS steam generators, the Department of Nuclear Engineering of the University of Palermo in collaboration with the ...
Casamirra, M +6 more
core
Thermal hydraulic simulations of the Angra 2 PWR
Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant is a pressurized water reactor (PWR) type with electrical output of about 1350 MW.
González-Mantecón Javier +6 more
doaj +1 more source

