Spelling suggestions: "subject:"powerplants"" "subject:"controlplants""
311 |
A heterogeneous finite element method and a leakage corrected homogenization techniqueNichita, Eleodor Marian 12 1900 (has links)
No description available.
|
312 |
Studies of turbulent liquid sheets for protecting IFE reactor chamber first wallsReperant, Jefferey John Robert 08 1900 (has links)
No description available.
|
313 |
Effect of condenser design upon boiler feedwater essergy costs in power plantsSmith, Mark Stevens 05 1900 (has links)
No description available.
|
314 |
In vitro dissolution of strontium titanate to estimate clearance rates in human lungsAnderson, Jeri L. 12 1900 (has links)
No description available.
|
315 |
Analysis of the antineutrino rate during CANDU reactor startupMatthews, Christopher 27 January 2012 (has links)
Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to visual inspections and intrusive monitoring systems. The recent development of antineutrino detectors may soon allow real-time monitoring from an unobtrusive location. Antineutrinos are produced through beta decay of fission products in the core. The lack of charge and small mass of the antineutrino ensures an extremely low interaction probability with all matter, effectively making the particle impossible to shield. As the fuel isotopic composition changes with burn-up, the primary fission source changes from ²³⁵U to ²³⁹Pu. Since differing antineutrino energy spectra are produced by each fissionable isotope, the antineutrino flux will also change as a function of burn-up. Supported by reactor simulations from nuclear codes, antineutrino detectors may provide a window into the reactor core and provide inspectors with tools to verify legitimate operations.
This thesis is focused on the antineutrino rate produced by CANadian Deuterium Uranium reactors (CANDU) during startup. A CANDU fuel bundle model was created with the TRITON module from the SCALE6.1 code to calculate isotopic antineutrino rates for a single bundle. A full core CANDU model that incorporates refueling was also created for the first 155 days of operation after startup by using a Python 2.6 script to handle pre- and post-calculations. All simulations were calculated using operational data from Point Lepreau Generating Station produced by proprietary codes for the forthcoming fresh core startup.
Dependence of the antineutrino rate on power and bundle replacement was analyzed, with a ±10% change in power causing a ±10% change in antineutrino rate, and the CANDU detector effectively measuring a 10% decrease in power within 9 hours of collection time. Bundle refueling was shown to only slightly modify the antineutrino rate, requiring a target volume more than 20 times larger than the present detector to effectively identify the change due to the bundles refueled over a one week period. Diversion of 15% or more of the total amount of bundles can be effectively measured by the CANDU detector within a one month counting period. / Graduation date: 2012
|
316 |
Wind turbine capacity planning approximations for northwest United States utilitiesEdinger, Chad L., January 2008 (has links) (PDF)
Thesis (M.S. in electrical engineering)--Washington State University, May 2008. / Includes bibliographical references (p. 90-95).
|
317 |
Multivariable robust control of a simulated hybrid solid oxide fuel cell gas turbine plantTsai, Alex, January 1900 (has links)
Thesis (Ph. D.)--West Virginia University, 2007. / Title from document title page. Document formatted into pages; contains xiv, 273 p. : ill. (some col.). Includes abstract. Includes bibliographical references (p. 184-189).
|
318 |
Design and development of train-the-trainer instruction for subject matter experts using intranet-based interactive multimediaWinn, Gloria Nave. Rhodes, Dent. January 2006 (has links)
Thesis (Ed. D.)--Illinois State University, 2006. / Title from title page screen, viewed on February 4, 2008. Dissertation Committee: Dent M. Rhodes (chair), Ellen A. Spycher, Chandra Sommers, Kenneth F. Jerich. Includes bibliographical references (leaves 109-117) and abstract. Also available in print.
|
319 |
Analysis and monitoring of a CANDU nuclear power plant using multivariate statistical process control methods /Leger, Robert P. January 1999 (has links)
Thesis (Ph.D.) -- McMaster University, 1999. / Includes bibliographical references (leaves [188]-192). Also available via World Wide Web.
|
320 |
Variables influencing fish impingement at five Alabama Power steam plantsSaalfeld, David Thomas. Bayne, David Roberge, January 2006 (has links) (PDF)
Thesis(M.S.)--Auburn University, 2006. / Abstract. Vita. Includes bibliographic references.
|
Page generated in 0.049 seconds