Open Access. Powered by Scholars. Published by Universities.®
- Discipline
- Keyword
-
- Accident Tolerant Fuel (1)
- Boiling heat transfer CHF Machine learning (1)
- Computed Tomography (1)
- Corrosion (1)
- Cosmic-Ray Muons (1)
-
- Critical Heat Flux (1)
- Detector Response (1)
- Electrochemistry (1)
- FLiBe (1)
- FeCrAl (1)
- Flow Boiling (1)
- Flow accelerated (1)
- Fuel Casks (1)
- In-motion (1)
- Machine Learning (1)
- Numerical model (1)
- Packed-Bed FHR (1)
- Simulation (1)
- Small and very small modular reactors; Walk-away safe; UN Fuel; Natural circulation; portable; long-life; distributed grid; Passive operation; Walk-away safe; Auxiliary electric power; Thermoelectric conversion. (1)
- Steady-state CHF (1)
- Support Vector Machine (1)
- Test loop (1)
- Transient CHF (1)
- Wireless pebble (1)
Articles 1 - 7 of 7
Full-Text Articles in Engineering
Experimental Investigation Of Steady-State And Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee
Experimental Investigation Of Steady-State And Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee
Nuclear Engineering ETDs
The Critical Heat Flux (CHF) causes a rapid reduction of heat transfer coefficient with a rapid increase of cladding temperature, which may induce physical failure of the heated material. Understanding CHF phenomena and reliable prediction of the boiling behavior are needed to design a heat transfer system including nuclear reactors. Due to the complex nature of CHF, it is still an active research topic of interest. With an increasing interest in Accident Tolerant Fuel (ATF), CHF of ATF is essential topic of study for the detailed design of the fuel – cladding element and for the reactor safety analysis.
In …
Neutronic And Cfd-Thermal Hydraulic Analyses Of Very-Small, Long-Life, Modular (Vsllim) Reactor, Luis M. Palomino
Neutronic And Cfd-Thermal Hydraulic Analyses Of Very-Small, Long-Life, Modular (Vsllim) Reactor, Luis M. Palomino
Nuclear Engineering ETDs
Neutronic and CFD-thermal hydraulic analyses are performed of the Very-Small, Long-LIfe, and Modular (VSLLIM) nuclear reactor. This reactor was developed at the University of New Mexico’s Institute for Space and Nuclear Power Studies (UNM-ISNPS) to generate 1.0 – 10 MWth for extended periods without refueling. It offers passive operation and safety features and redundant control and would be fabricated, assembled and sealed in the factory. During nominal operation and after shutdown, the VSLLIM is cooled by natural circulation of in-vessel liquid sodium, with the aid of an in-vessel chimney and annular helically-coiled …
Interrogation Of Spent Nuclear Fuel Casks Using Cosmic-Ray Muon Computed Tomography, Daniel C. Poulson
Interrogation Of Spent Nuclear Fuel Casks Using Cosmic-Ray Muon Computed Tomography, Daniel C. Poulson
Nuclear Engineering ETDs
Properly accounting and safeguarding spent nuclear fuel are key components in the International Atomic Energy Agency’s mission of non-proliferation. Currently, no instruments are deployed that are able to verify the spent nuclear fuel contents of dry storage casks. Cosmic-ray muons provide an ideal probe for the heavily shielded casks due to their ability to penetrate thick, dense materials. Coulombic scattering of the muons, to first order, is proportional to the Z2/A of the material; this makes it especially sensitive to actinides, such as uranium and plutonium. The combination of these traits allows muons to be used to image and verify …
Developing A Simulation Tool For Evaluating In-Motion Detector Systems (La-Ur-18-29139), Brian Jennings
Developing A Simulation Tool For Evaluating In-Motion Detector Systems (La-Ur-18-29139), Brian Jennings
Nuclear Engineering ETDs
Available simulation software lacks the ability to produce in-motion detector responses for detector systems that may be used to detect the illicit trafficking of nuclear materials. In this thesis, a simulation tool is developed that uses static measured data as a basis set for producing in-motion detector responses with the ability to vary many parameters in each simulated trial. Once the basis set is measured and loaded into the simulation tool, the user interface allows the user to enter variations to speed, source height, source-to-detector distance, background exposure rate, which source(s) are present, their relative strength and shielding configuration, and …
Development Of Wireless Pebble For Packed Bed Heat Transfer Measurements And Machine Learning-Aided Accident Diagnosis For Loss Of Flow Accident (Lofa), Dongjune Chang
Nuclear Engineering ETDs
In the first study, a novel wireless pebble for scale experiments is developed, and a simple heat transfer experiment is conducted to determine the difference in the local heat transfer coefficient. Based on the fact that the use of Dowtherm A between approximately 57–87 °C is an alternative to the normal use of the FliBe temperature range of 600–700°C, a new-concept wireless device in a scaled experiment is introduced. This device consists of a 63.5 mm diameter metal shell and contains a built-in customized circuit board and battery for driving temperature measurements and wireless data transfer. The circuit board used …
Application Of Machine Learning To Chf Modelling, Mingfu He Mr
Application Of Machine Learning To Chf Modelling, Mingfu He Mr
Nuclear Engineering ETDs
Accurate prediction of CHF is still a challenging issue in the study of boiling heat transfer. Many factors contribute to the occurrence of CHF and the various trigger mechanisms are proposed to unravel physical phenomena behind CHF. However, those mechanisms cannot cover the multiple primary factors simultaneously and even some of them still remain controversially unresolved. In light of the complexity and difficulty of CHF modelling, hereby an ensemble-learning based framework is proposed to model and predict CHF based on the databank of CHF. Some prior trials have been done for three primary aspects of dominant factors, that is, surface …
An Experimental And Numerical Investigation Of Flow Accelerated Flibe Corrosion, David B. Weitzel
An Experimental And Numerical Investigation Of Flow Accelerated Flibe Corrosion, David B. Weitzel
Nuclear Engineering ETDs
Renewed interest in molten salt reactor technology has brought to light the need for a better understanding of FLiBe corrosion. To this end a flowing FLiBe corrosion test loop was designed to test the flow effects of FLiBe corrosion. The loop consists of a pump, melt tank, and stainless-steel tubing assembly that heats the molten salt to high temperatures and circulates it over test specimens. The experiment has been constructed and has completed initial shakedown testing.
To support the flowing FLiBe experiment, a numerical corrosion model that couples FLiBe electrochemistry, solid metal diffusion, and mass transport was implemented. The model …