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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.
21

Power spectral density of the detection process in a boron triflouride [sic] neutron detector

Mecredy, Robert Clark. January 1968 (has links)
Thesis (M.S.)--University of Michigan, 1968.
22

PANDA a planar (x-y), two-group neutron diffusion analysis program /

Schwartz, Michael H. January 1972 (has links)
Thesis (M.S.)--University of Michigan, 1972.
23

A technique for measuring the neutron age

De Lizarriturri, Gerardo. January 1900 (has links)
Thesis (M.S.)--University of Michigan, 1958.
24

Measurement of the 1.46-ev flux distribution in a small polyethylene moderator using In-In activation methods

Pantazatos, Peter. January 1971 (has links)
Thesis (M.S.)--University of Michigan, 1971.
25

Exploration of several radiation-based Analytical techniques to investigate Chlorides and Effects within concrete/

Radebe, Mabuti Jacob. Unknown Date (has links) (PDF)
Thesis (M.Sc. Physics) -- University of the Western Cape, 2007. / Includes bibliographic references (leaves 103-111).
26

A theoretical comparison of 4[pi] fast-neutron spectrometers

Kim, Chul Mo. January 1961 (has links)
Thesis (M.S. in Engineering Science)--University of California, Berkeley, June 1961. / "UCRL-9504." Bibliography: leaves 66-69.
27

Some aspects of the neutron flux distribution in fuel rods and in moderator and the effect of removal of a single fuel rod in the subcritical assembly of the University of Michigan

Khang, Nguyen-Thuong-. January 1962 (has links)
Thesis (M.S.)--University of Michigan, 1962.
28

Contribution à l'étude des détecteurs de localisation à haute résolution géométrique pour neutrons thermiques.

Idrissi Fakhr-Eddine, Abdellah, January 1900 (has links)
Th. 3e cycle--Instrumentation nucl.--Grenoble 1, 1978. N°: 118.
29

Eigenvalue methods for time-dependent neuton diffusion

Oliveira, Roberto Gomes de, Instituto de Engenharia Nuclear 05 1900 (has links)
Submitted by Marcele Costal de Castro (costalcastro@gmail.com) on 2017-12-14T13:31:22Z No. of bitstreams: 1 ROBERTO GOMES DE OLIVEIRA D.pdf: 3867483 bytes, checksum: 78ad2fbf8f7d233065438b4f60942947 (MD5) / Made available in DSpace on 2017-12-14T13:31:22Z (GMT). No. of bitstreams: 1 ROBERTO GOMES DE OLIVEIRA D.pdf: 3867483 bytes, checksum: 78ad2fbf8f7d233065438b4f60942947 (MD5) Previous issue date: 1969-05 / The analysis of pulsed neutron experiments in multiplying and in nonmultiplying domains is considered. The analysis is based on the one-dimensional diffusion theory modelo In one-group models, a scalar version of problems similar to those of Sturm Liouville systems is generated; while in multigroup models, a vector version is required. An algorithm is suggested which allows the complete solution of the general scalar problem in all separable geometries of interest, for homogeneous boundary conditions. The results are the time igenvalues and the spatial eigen functions. The algorithm is suitable for direct computer implementation. Examples of application are given. The multigroup problem can be solved by adequate extensions of the one-group algorithm. Since the associated operators are nonselfadjoint, the eigenvalues form in general a spectrum that has a discrete plus a continuous part. All of the discrete spectrum can be obtained using the suggested method. An example with two groups of neutrons in a three-region domain is given. Extensions to inhomogeneous equations and boundary conditions are considered. Application of the methods to other problems rather than the pulsed neutron problem are studied. The method is shown to be useful in the solution of nonlinear boundary-value problems. Pulsed neutron experiments can be analyzed as problems similar to Sturm-Liouville systems. The scalar problems are completely solved here. The vector problems are partially solved. Some progress in the mathematical theory of nonselfadjoint operators is required for the complete solution of the vector problem.
30

Design, Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory

Turkoglu, Danyal J. January 2011 (has links)
No description available.

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