Visar resultat 1 - 5 av 13 avhandlingar innehållade ordet thermal-hydraulics.
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
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. Application of a system thermal-hydraulics code to development of validation process for coupled STH-CFD codes
Sammanfattning : Generation IV reactors are designed to provide sustainable energy generation, minimize waste production and excel in safety. Due to lack of operational experience, ever evolving design and stringent safety requirements, these novel reactors have to rely heavily on simulations. LÄS MER
Sammanfattning : This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions of the behavior of Light Water Reactor (LWR) cores. The multiphysics aspects cover the distribution of neutrons, the fluid flow of the coolant and the conjugate heat transfer between the solid fuel pins and the fluid coolant. LÄS MER
Sammanfattning : The best estimate codes are used for licensing of Nuclear Power Plants (NPP), but with conservative assumptions. It is claimed that the uncertainties are covered by the conservatism of the calculation. LÄS MER