Global ETD Search

1	ECC bypass study an evaluation of various models / Colby, Mark J. January 1977 (has links) Thesis (M.S.)--University of Michigan, 1977.
2	An economic optimization of pressurized light water reactor cores Pfeifer, Holger 12 1900 (has links) No description available. Pressurized water reactors Cores
3	Nuclear methods for the determination of boron concentration in solutions Caroll, Carmine R. January 1900 (has links) Thesis (M.S.)--University of Michigan, 1971. Pressurized water reactors
4	UW-4F a mechanistic four-fluid two-phase flow model for LOCA analysis during reflood / Summers, Randall Mark. January 1981 (has links) Thesis (Ph. D.)--University of Wisconsin--Madison, 1981. / Typescript. Vita. Description based on print version record. Includes bibliographical references (leaves 231-240). Pressurized water reactors
5	The study of cold leg thermal stratification in APEX-CE Antoine, Stephanie Y. L. Antoine 30 April 2002 (has links) This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory Commission's (USNRC) re-evaluation of its PTS regulations. Using the APEX-CE test facility, thermal stratification was observed for injection flow rates ranging from 30% to 100% and natural circulation flow rates that were generated by core decay powers ranging from 1.5% to 4%, both relative to the scaled Palisades values. A theoretical model was derived to estimate the hot stream entrainment that occurs during cold leg thermal stratification. This model was applied to the Separate Effects Transparent Loop (SETL) facility, a scaled cold leg/downcomer configuration of the APEX-CE plant. The model predictions were in reasonable agreement with the High Pressure Injection (HPI) fluid entrainment data from the Purdue ½ scale facility. The same model was then used to estimate HPI entrainment in SETL. The results proved to be very consistent. Finally, data for the onset of loop seal spillover was obtained using SETL and APEX-CE. A useful flow map, characterizing the onset condition, was generated. / Graduation date: 2002 Thermal stresses Pressurized water reactors
6	Pressure losses across a 180 degree turn in the AP1000 cooling annulus / Nelson, Roy K. January 1900 (has links) Thesis (M.S.)--Oregon State University, 2009. / Printout. Includes bibliographical references (leaves 80-84). Also available on the World Wide Web.
7	Implementation of the Michigan Thermal Hydraulic Analysis Code (MITH) in 2DB(UM) for coupled neutronic-thermal hydraulic calculations master's thesis / Ardeshiri, Farzad. January 1984 (has links) Thesis (M.S.)--University of Michigan, 1984.
8	Turbine steam purity in nuclear once through units master's project / Soi, Satyadev N. January 1980 (has links) Thesis (M.S.)--University of Michigan, 1980.
9	In-core optimisation of thorium-plutonium-fuelled PWR cores Zainuddin, Nurjuanis Zara January 2015 (has links) No description available. 620
10	LWR fuel performance analysis : fuel cracking and relocation Maki, John T., Meyer, John E. 10 1900 (has links) "Final report for research project sponsored by Northeast Utilities Service Company, Yankee Atomic Electric Co. under the MIT Energy Laboratory Electric Utility Program." Pressurized water reactors. Nuclear fuel elements.

Search results