- 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.
Search results
Showing 1 to 10 of 18 (0.123 seconds)Spelling suggestions: "subject:"buclear reactors -- cafety measures."" "subject:"buclear reactors -- asafety measures.""
| 1 |
An investigation of nuclear excursions to determine the self-shutdown effects in thermal heterogeneous, highly enriched, liquid-moderated reactorsFagan, John Robert. January 1962 (has links)
Call number: LD2668 .T4 1962 F35
|
| 2 |
Doppler broadening induced spectral shift effects on reactor safetyAlapour, Adel 05 1900 (has links)
No description available.
|
| 3 |
Control system modeling for a boiling water reactorMowrey, James A. 05 1900 (has links)
No description available.
|
| 4 |
Monte Carlo based exposure rate response estimates for criticality accident detectors at the Savannah River siteZino, John Frederick 12 1900 (has links)
No description available.
|
| 5 |
Examination of offsite radiological emergency protective measures for nuclear reactor accidents involving core meltAldrich, David Charles January 1978 (has links)
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.
|
| 6 |
Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactorsAl-Kheliewi, Abdullah S. 20 September 1993 (has links)
A transient code (TFETC) for calculating the temperature
distribution throughout the radial and axial positions of a
thermionic fuel element (TFE) has been successfully developed.
It accommodates the variations of temperatures, thermal power,
electrical power, voltage, and current density throughout the
TFE as a function of time as well as the variations of heat
fluxes arising from radiation, conduction, electron cooling,
and collector heating. The thermionic fuel element transient
code (TFETC) is designed to calculate all the above variables
for three different cases namely: 1) Start-up; 2) Loss of flow
accident; and 3) Shut down.
The results show that this design is suitable for space
applications and does not show any deficiency in the
performance. It enhances the safety factor in the case of a
loss of flow accident (LOFA). In LOFA, it has been found that
if the mass flow rate decreases exponentially by a -0.033t,
where t is a reactor transient time in seconds, the fuel
temperature does not exceed the melting point right after the
complete pump failures but rather allows some time, about 34
seconds, before taking an action. If the reactor is not shut
down within 34 seconds, the fuel temperature may keep
increasing until the melting point of the fuel is attained. On
the other hand, the coolant temperature attains its boiling
point, 1057 ��K, in the case of a complete pump failure and may
exceed it unless a proper action to trip the reactor is taken.
For 1/2, 1/3, and 1/4 pump failures, the coolant temperatures
are below the boiling point of the coolant. / Graduation date: 1994
|
| 7 |
Acoustical boiling detection system for natural convection pool-type reactorsVidalin, William Edward January 1978 (has links)
No description available.
|
| 8 |
The effect of countercurrent flow limitation in small passagesBohner, John David 12 1900 (has links)
No description available.
|
| 9 |
Post critical heat flux heat transfer in a vertical tube including spacer grid effectsCluss, Edward Max January 1978 (has links)
Thesis. 1978. M.S.--Massachusetts Institute of Technology. Dept. of Mechanical Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING. / Includes bibliographical references. / by Edward M. Cluss, Jr. / M.S.
|
| 10 |
Population estimates and projections for nuclear power plant safety analyses and evacuation plans : the Shoreham nuclear power station methodologyDonnelly, Kathleen A January 2010 (has links)
Typescript (photocopy). / Digitized by Kansas Correctional Industries
|
Page generated in 0.1304 seconds