Nuclear Engineering Commons^™

Calculation Of Neutron Flux And Neutron Radiation Dose In A Human Phantom, L. Alan Smith

Opportunities for Undergraduate Research Experience Program (OURE)

At present, the neutron dose received by personnel working in nuclear installations is recorded by body surface dosimeters worn by workers. To estimate the true neutron dose to internal organs, this ’surface dose” is multiplied by empirical factors to account for the attenuation of the body itself.

The objective of this work was to obtain better estimates of the internal dose by calculating the attenuation of the neutron flux provided by the body. Using DOT, a 2-D radiation transport code, the neutron flux as a function of energy was calculated at several points in a 2-D model of the human …

Solution Of Divertor Magnetohydrodynamic Equilibria For The Study Of Alpha Particle Edge Transport In Fusion Plasmas, J. W. Schumer

Opportunities for Undergraduate Research Experience Program (OURE)

Removal of thermalized alpha particles from deuterium- tritium (D-T) fusion plasmas can be accomplished through the use of divertor magnetic fields if the magnetohydrodynamic (MHD) equilibria is well understood [1]. Modifying a MHD variational energy principle for poloidal flux surfaces described by 𝒳 = 𝒳(ρ, θ) results in an inverse Fourier representation of the three-dimensional (3-D) equilibria solution. Application of the 𝒳 = 𝒳(ρ, θ) flux profile allows transformation of the magnetic field into a non-singular coordinate system along the divertor separatrix [2] and therefore, analysis of different divertor schemes. Derivation of the coupled, non-linear differential equations follows [5] except …

A Heat Balance Program For A Nuclear Power Plant, Timothy C. Steadham

Opportunities for Undergraduate Research Experience Program (OURE)

In a coal fired power plant, the steam leaving the boiler can reach 1000 °F and 3000 psia; this state is superheated considerably. On the other hand, a nuclear power plant is not capable of reaching such conditions without compromising reactor safety and integrity. Therefore, the steam leaving the reactor might only be a few degrees superheated, and hence the steam leaving each turbine will be wet. Since wet steam will erode turbine blades very quickly, devices must be placed between turbines to separate the steam into saturated vapor and saturated liquid. The steam is routed through the next turbine …

A Mathematical Model And Simulation Of Natural Circulation Loop Thermalhydraulics, Nihad E. Daidzic

Aviation Department Publications

In this work, a simple, nonlinear, seventh-order mathematical model with lumped parameter analysis of the thermalhydraulic processes in a natural circulation steam boiler loop is presented. Digital simulation has been performed in order to predict open loop transients in severe accidental situations. Parts of the circulation loop such as the steam drum, downcomer, and riser were modelled separately on the basis of the integral balance equations. The two-phase flow in the steam drum and in the riser was modelled with the aid of a homogeneous-equilibrium, two-phase flow model. Special care was taken to ensure the stability of the numerical scheme, …

Sensor Signal Analysis By Neural Networks For Surveillance In Nuclear Reactors, Shahla Keyvan

Nuclear Engineering and Radiation Science Faculty Research & Creative Works

The application of neural networks as a tool for reactor diagnostics is examined here. Reactor pump signals utilized in a wear-out monitoring system developed for early detection of the degradation of a pump shaft [17] are analyzed as a semi-benchmark test to study the feasibility of neural networks for monitoring and surveillance in nuclear reactors. The Adaptive Resonance Theory (ART 2 and ART 2-A) paradigm of neural networks is applied in this study. The signals are collected signals as well as generated signals simulating the wear progress. The wear-out monitoring system applies noise analysis techniques and is capable of distinguishing …