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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
1

Water-cooled Heat Sink in Finite Element Analysis

Guo, Heng-shen 12 August 2009 (has links)
Abstract With the development of computer processors, the size of chip has become smaller. But the processors used in high-power needs high performance of heat dissipation. In electronic design of the thermal management, the heat sink is the most basic application. Since the natural convection can not cool down effectively, it needs to use the forced convection cooling. The purpose of this study explored water-cooled sink as the heat source for the high-power chip. The study findings show that the ATC cooling chip enhances the potency and decreased the noise. Most importantly, it dissipates heat. In the present study, the researcher used Computational Fluid Dynamics to analyze the heat flow problem. By applying three variables in terms of the flow channel, the housing size, and the heat sink size in data analyses, the researcher classified different types of water-cooled sink. From the discussion of different flow rate and the thermal resistance, it shows that the trend curve of the fin-gilled sink is different from others. It also shows that it performs better in the low flow rate. After all using each method of heat dissipation, the potency of N-type channel sink is the best. When flow rate is 2.2 L/min, the thermal resistance is 0.0971˚C/W.
2

Statistical hot channel analysis

Spong, Donald A. January 1971 (has links)
Thesis (M.S.)--University of Michigan, 1971. / eContent provider-neutral record in process. Description based on print version record.
3

Effect of additives on pool boiling of water

Rouai, Neffati Moamer. January 1982 (has links)
Thesis (M.S.)--University of Wisconsin--Madison, 1982. / Typescript. eContent provider-neutral record in process. Description based on print version record. Includes bibliographical references (leaves 81-82).
4

Analysis of the offsite consequences of a loss-of-coolant-accident in a power reactor

January 1971 (has links)
Thesis (M.S.)--University of Michigan, 1971.
5

Control system modeling for a boiling water reactor

Mowrey, James A. 05 1900 (has links)
No description available.
6

All-Metal water target with spherical window

Gelbart, W., Johnson, R. R., Abeysekera, B., Matei, L., Niculae, D. 19 May 2015 (has links) (PDF)
Introduction The use of a prefabricated target window assembly greatly simplifies the window installation. The window module is sealed by metal knife-edges, thus eliminating any elestomers in the target construction. Spherical Havar window offers high strength at reduced thickness and does not require helium cooling. The target body is of platinum-plated silver. The target assembly includes an integral beam collimator and a four-sector mask.
7

Development of a simulation model for PWR reactor coolant system /

Chan, Ping-lam. January 1989 (has links)
Thesis (M. Phil.)--University of Hong Kong, 1990.
8

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Merritt, Patrick A. 15 December 1999 (has links)
Graduation date: 2000
9

Analysis and proposed revision of the radiation protection and waste management programs as described in the Oregon State University TRIGA research reactor safety analysis report

Chinudomsub, Kittisak 26 May 1999 (has links)
The Safety Analysis Report (SAR) of the Oregon State University TRIGA Research Reactor (OSTR) was prepared and used as a safety baseline for the reactor's operation since 1968. Although, in general, revision of the Safety Analysis Report of a research reactor is not a regulation requirement, it should be revised from time to time to include changes to the facility or procedures or update to current regulatory standards. The ANS 15.21 workgroup developed a draft standard format and content for safety analysis reports for research reactors. An area of this guidance, which was selected for this work's revision of OSTR-SAR, is the radiation protection program and waste management chapter. The Health Physics program of the facility was observed. The radiological data were obtained from the annual reports for more than 10 years of operation. The related data, such as meteorological data, were obtained and prepared for the analysis processes. The current federal regulation limits and recommendations were used as the references for dose assessments. The results show the OSTR has a sufficient radiation protection program not only for the facility's workers, but also for the general public, and the program is in full compliance with the federal regulations. The dose estimation shows that the workers and general public can not receive and have not received doses in excess of regulatory limits from the normal operation of the OSTR. / Graduation date: 2000
10

Development of a simulation model for PWR reactor coolant system

陳炳林, Chan, Ping-lam. January 1989 (has links)
published_or_final_version / Mechanical Engineering / Master / Master of Philosophy

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