Design criteria for phase II dummy hydraulic core for containment systems experiment reactor simulator
Charles H. Henager
Abstract
Open-access reader
Charles H. Henager
Abstract
Open-access reader
The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefaction wave pressures during high temperature, high pressure blowdown studies.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefaction wave pressures during high temperature, high pressure blowdown studies.
Key concepts: Thermal hydraulics, Baffle, Core (optical fiber), Nuclear engineering, Mockup, Nuclear reactor core, Boiler blowdown, Control rod