Sökning: "thermal hydraulic system code"

Visar resultat 6 - 8 av 8 uppsatser innehållade orden thermal hydraulic system code.

1. 6. Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems

   Master-uppsats, KTH/Fysik

   Författare :Marti Jeltsov; [2011]
   Nyckelord :Coupled Codes; Verification Validation; CFD; System Thermal-Hydraulics; Lead Cooled sys-;

   Sammanfattning : Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety analysis as a tool that enables safety related physical phenomena occurring in the reactor coolant system to be described in more detail and accuracy. Validation is a necessary step in improving predictive capability of a computationa code or coupled computational codes. LÄS MER

3. 7. Analysis of Advanced Fuel Behaviour during Loss of Coolant Accident in Swedish Boiling Water Reactor

   Master-uppsats, KTH/Kärnkraftssäkerhet

   Författare :Paul Breijder; [2011]
   Nyckelord :Accident analysis; BWR; LOCA; sensitivity study; thermal hydraulic system code; TRACE;

   Sammanfattning : In accident analysis regarding nuclear power plants, it is very common to use thermal hydraulic system codes, such as TRACE, developed by U.S. NRC. In the case of licensing a power plant, this is one of the necessities. LÄS MER

4. 8. TRACE Analysis for Transient Thermal-hydraulics of A Heavy Liquid Metal Cooled System

   Master-uppsats, KTH/Kärnkraftssäkerhet

   Författare :Yiqiong Shao; [2011]
   Nyckelord :;

   Sammanfattning : Heavy liquid metal (HLM - lead or lead bismuth eutectic) is considered as a candidate coolant for next-generation fast reactor and accelerate-driven systems (ADS), due to its favorable chemical, thermo-physical and neutronic properties in comparison with sodium which has been used as coolant in fast breeder reactors (FBRs). To perform design-base-accident analysis for the HLM-cooled reactors, the well-known transient thermal-hydraulic analysis codes (e. LÄS MER