The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
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Wade R. Marcum
The understanding of critical heat flux is crucial for the safety of nuclear
There are efforts underway at Idaho National Laboratory to design, modify, and implement an array of techniques into a nuclear material ready Scanning Electron Microscope (SEM) to accelerate comprehensive characterization of the physical properties and microstructures of irradiated fuels and materials. The goals of adding a micro four-point probe (M4PP)...
The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
Power transient boiling has been studied for decades, however, the mechanistic understanding of phenomena which occur during such an event remains incomplete. Due to a dearth of systematic researches, the information of studied phenomenon, detailed physics and applicable hypothesis are very limited. Transient critical heat flux (CHF) is paramount in...
The subject of fluid-structure interactions (FSI) are a matter concerning the design of any element immersed in a fluid. One of the most critical phenomena embedded within the scope of FSI is the creation of vortex-induced vibrations (VIV). These type of vibrations originate in a given body as a result...
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Wade R. Marcum
The subject of fluid-structure interactions (FSI) are a matter concerning
One of the most important components in the safety analysis of a nuclear reactor is its critical heat flux (CHF), as it can compromise the structural integrity of the clad and lead to the release of fission products into the primary coolant. Groeneveld et. al. has published a series of...
The International Atomic Energy Agency (IAEA) is the leading organization for monitoring nuclear facilities worldwide, and the Agency’s methods are constantly developing and improving in an effort to more effectively safeguard nuclear material. As such, the IAEA addresses near and long term risks in order to advance the capabilities of...
As computational power increases, so does the desire to use fluid-structure interaction (FSI) software to design complex systems and components such as fuel plates. Presently, an effort is underway to support the design and qualification of a new nuclear fuel material which is intended for applications in select, plate-type, research...
A set of experimental plates were characterized to understand their dynamic response in both air and water; in support of work performed at the Hydro-Mechanical Fuel Test Facility and the Global threat Reduction Initiative. In an attempt to gain further insight into the vibration of the experimental test plates, a...
The Advanced Test Reactor (ATR), under the Reduced Enrichment for Research and Test Reactors (RERTR) Program and the Global Threat Reduction Initiative (GTRI), is conducting feasibility studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low enriched uranium (LEU) composition. These studies have...