Sökning: "Feedwater Transient"
Hittade 3 avhandlingar innehållade orden Feedwater Transient.
1. Effective Spatial Mapping for Coupled Code Analysis of Thermal–Hydraulics/Neutron–Kinetics of Boiling Water Reactors
Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal–hydraulics (TH) codes. In order to produce results within a reasonable computing time, the coupled codes use two different spatial description of the reactor core. LÄS MER
2. Development of Effective Algorithm for Coupled Thermal-Hydraulics – Neutron-Kinetics Analysis of Reactivity Transient
Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal-hydraulics (TH) codes. To produce results within a reasonable computing time, the coupled codes use different spatial description of the reactor core. LÄS MER
3. Development and Applications of a General Coupled Thermal-hydraulic/Neutronic Model for the
Sammanfattning : Coupled calculations are important for the simulation of nuclear power plants when there is a strongfeedback between the neutron kineticsand the thermal-hydraulics. A general coupled model of the Ringhals-3 Pressurized Water Reactor has beendeveloped for this purpose. LÄS MER