Nuclear Engineering Commons^™

Computational Methods, Investigations, And Codes To Support Corrosion Experiments In Molten Lead And Transfer To Reactor Conditions, Khaled A. Talaat

Nuclear Engineering ETDs

Lead cooled fast reactors have many potential economic advantages over other Generation IV reactor designs due to the high boiling point of lead (~1750 °C) at atmospheric pressure and excellent neutronic properties which have made them attractive to the commercial energy sector in the recent years. They, however, remain hampered by challenges in cladding material compatibility with the heavy liquid metal coolant. A forced circulation loop was established at the University of New Mexico (“Lobo Lead Loop”) to prequalify materials for Versatile Test Reactor (VTR) testing and to improve the understanding of flow accelerated corrosion in molten lead environment. Corrosion …

Joining Of Candidate Materials For Lead-Cooled Fast Reactors, Brandon M. Bohanon

Nuclear Engineering ETDs

The lead-cooled fast reactor (LFR) is a fourth-generation reactor design characterized by high temperatures, neutron dosage, and highly corrosive and erosive environment due to high flow velocities. Therefore, materials testing must be performed to find structural and system components that withstand this harsh environment. These candidate alloys must have high-temperature creep strength, resistance to damage from fast-spectrum neutrons, and must grow protective oxide layers. FeCrAl alloys have been identified as possessing all these qualities, however, there are limitations due to erosion and the joining of these materials. In this work, mechanical and microstructural properties of base and conventionally joined FeCrAl-based …

The Effects Of A Power Iteration-Based K-Eigenvalue Solver For Various Subcritical Parameters And Calculations, Daniel H. Timmons

Nuclear Engineering ETDs

The need to simulate subcritical benchmark parameters quickly and accurately is becoming increasing important. When using Monte Carlo methods this is traditionally done using a fixed-source calculation where a particle and its progeny are tracked until their removal from the system. This method can be slow for near critical systems. The use of a k-eigenvalue solver could reduce the computational footprint and reduce the need to post process data.

This is done for four parameters from the ICSBEP benchmark values: R_1 , R_2 , M_L, and M_eff. These parameters are calculated in two new distinct ways. First, is directly …

Simulation Of Thermal Radiation Transport In Stochastic Media With Nonlinear Temperature Dependence, Corey Michael Skinner

Nuclear Engineering ETDs

Nonlinear gray thermal radiation transport (TRT) in binary statistical mixtures is investigated through Implicit Monte Carlo (IMC) simulation on one-dimensional planar Markovian geometries and two dimensional approximate Markovian or Poisson-Box geometries. A stochastic geometry option was implemented in the Los Alamos National Laboratory Branson IMC solver which yielded benchmark solutions by simulating thermal radiation and material energy transport over a large number of instantiations of the geometry followed by ensemble averaging to obtain conditionally averaged radiation intensity and material temperatures. A chord length sampling method was also implemented based on a heuristic generalization of the Levermore-Pomraning homogenized medium model to …

Experimental Investigations On Boiling Heat Transfer Characteristics Of Accident-Tolerant-Fuel And Traditional Claddings, Mingfu He Mr.

Nuclear Engineering ETDs

To make it more clear that how the materials’ thermal-physical properties and wall thickness have influential impacts on boiling heat transfer characteristics of cladding, this dissertation looks into the potential impacts of cladding materials on critical heat flux and heat transfer coefficients by a systematic experimental investigation across a wide range of pool/flow boiling conditions under the steady-state and power-transient heat inputs.

Recent thermal-hydraulics studies have demonstrated that iron-chromium-aluminium (FeCrAl) alloys have the thermal priorities over zircaloys and other commercial alloys including critical heat flux and heat transfer coefficient. However, it is found in our experimental results that FeCrAl-C26M, and …

Utilizing Sensitivity And Correlation Coefficients From Mcnp And Whisper To Guide Microreactor Experiment Design, Alexis Maldonado

Nuclear Engineering ETDs

When designing experiments for full-scale reactor systems, MCNP and Whisper can be used to create neutronic models and compare the similarity of two nuclear systems via correlation coefficients for 𝑘𝑒𝑓𝑓, effective multiplication factor. This thesis applies this framework to a conceptual heat-pipe, yttrium-hydride moderated microreactor system and experiments. The framework is intended as a supplement to other neutronics/thermal/multiphysics analyses and provides a concrete method to measure the neutronic similarity of two systems. By analyzing the shared nuclear data uncertainty, as well as sensitivity to nuclear data over all neutron energies, highly informative experiments can be designed to aid in the …