Small Modular Reactors (SMRs) are currently being developed and licensed in many countries. The innovations the designs provide significant features, such as decreased construction cost time, enhanced safety, modularity, possibility of factory production etc. Several new SMR based on concept an integral Pressurized Water Reactor. One designs, namely NuScale was selected for this analysis. An in...

Post-Loss of Coolant Accident (LOCA) ductility assessments Cr-coated Zircaloy cladding was conducted in compliance with the United States Nuclear Regulatory Commission (U.S.NRC)’s guidelines. The Equivalent Cladding Reacted (ECR) limit for oxidized on both sides, representing embrittlement process an outer-side coated near burst hole followed by ballooning, is found to be 13.8% at steam oxidati...

The Breeding Blanket (BB) is one of the key components European Demonstration (EU-DEMO) fusion reactor. Its main subsystems, Breeder Zone (BZ) and First Wall (FW), are cooled by two independent cooling circuits, called Primary Heat Transfer Systems (PHTS). Evaluating BB PHTS performances in anticipated transient accident conditions a relevant issue for design these systems. Within framework EUR...

Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, design, production, processing, and accident maintenance blankets all huge challenges traditional water/gas-cooled blankets. bridge heat transfer tritium production. A high-performance blanket with simplified structure is obviously beneficial engineering, safety, economy. In this study, gravity...

In this study, a multi-physics modeling method was developed to analyze nuclear fuel rod's thermo-mechanical behavior especially for high temperature anisotropic creep deformation during ballooning and burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer nonlinear mechanical analysis, the present work newly incorporated special characteristics which include gap t...