The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.
The objective of this project was to use the thermal hydraulics laboratory and vacuum test chambers at Oak Ridge National Laboratory (ORNL) for response characterization of resistance temperature detectors and thermal aging of instrumentation and control (I&C) cables in vacuum to generate more useful data for I&C cable derating purposes.
Framatome used failure modes and effects analysis (FMEA) to determine and define potential failure mechanisms for the U-50Zr alloy design.
General Electric-Hitachi, Argonne National Laboratory and the Idaho National Laboratory provided improved operational guidance for the current and advanced BWR off-gas system designs and identified off-gas system design improvements for use in BWR SMRs.
The objective of this project was to improve nuclear power generation’s safety and competitiveness by providing robust information about the flow patterns and formations throughout the simulated fluid domain.
The objective of this project was to determine if currently available technology can be used to modernize the PSP to a level of cost-effectiveness to realize the potential cost saving in the nuclear fuel cycle.
The objective of this project was to explore the primary flow stability of the SMR-160 and to investigate an unborated core and primary loop, which necessitates active reactivity control with control rods, and the straight tube, once-through steam generator.
The objective of this project was to determine what performance improvements could be found in Ceramic Tubular Products’ newly formulated silicon carbide (SiC) TRIPLEX cladding coating.