Thesis (M.S.)--University of Michigan, 1979.

Thesis (M.S.)--University of Michigan, 1969.

Thesis (M.S.)--University of Michigan, 1977. / Project completed in 1976. Degree awarded in 1977.

Fissile materials in the form of aqueous homogeneous solutions are used during the chemical processing of nuclear materials. In this form there exists the possibility of an accidental criticality. A one-dimensional multi-region model was developed for simulating fast power excursions in a cylinderical homogeneous aqueous fissile solution. The model includes a novel method for computing reactivity feedback that accounts for the axial distribution of power and solution density. The feedback method is based on the change in neutron leakage due to a change in solution density. The model also includes an equation of state derived from quasi-static thermodynamic theory for a solution containing gas bubbles. The model was compared to the KEWB-5 (Kinetic Experiments on Water Boilers) series of experiments. The model could approximate the values of peak power and pressure found in the experiments, but the pressure curves did not match the shapes of the experimental pressure traces.

Thesis (M.S.)--University of Michigan, 1957.

Thesis (M.S.)--University of Michigan, 1985. / Includes: Supplement: the time required for complete core meltdown of FNR under LOCA accident.

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An accidental criticality may occur in a solution of fissile material. Since the processing of nuclear materials in solution is prevalent throughout the fuel cycle, it would be judicious to have the capability to predict a possible hazard. In view of this concern, a computer simulation was performed of the Los Alamos accident of December 30, 1958, in which the actuation of an electric stirrer produced a sudden criticality. A complete equation of state for a liquid containing gas bubbles was coupled with the equations of energy, momentum, and space-independent point kinetics. Multiplication calculations, implemented with the Monte Carlo Code for Neutron and Photon Transport (MCNP), were performed on thermally expanding solution geometries, to generate a reactivity feedback representation. With the knowledge of the total energy produced in the accident, the maximum reciprocal period on which the power rose was computed.

Thesis. 1978. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by David C. Aldrich. / Ph.D.