Masters Theses

Abstract

"This investigation presents a mean to determine thermal neutron flux of a reactor by irradiating copper wires inside the fuel elements. The activity recorded after decay correction, is the relative thermal neutron density. Thermal neutron flux is a measure of the neutron density at thermal energy, 0.025 ev.

Gold foils irradiated at National Bureau of Standards were used as the absolute neutron flux calibration standards. The average flux of the reactor with water as the reflector ranges from 7.24 x 1010 neutrons/cm2 - sec. to 7.87 x 1010 neutrons/cm2 - sec. as obtained from the calculations. This set of values compares favorably with the result as measured by the manufacturers.

In this investigation the thermal neutron flux in the MSM reactor was determined by irradiating copper wires inside the fuel elements"--Abstract, page ii.

Advisor(s)

Pauls, Franklin B., 1911-1996

Committee Member(s)

McFarland, Charles E.
Kerr, Richard H., 1907-1980
Miles, Aaron J.

Department(s)

Physics

Degree Name

M.S. in Physics

Publisher

Missouri School of Mines and Metallurgy

Publication Date

1962

Pagination

vii, 72 pages

Note about bibliography

Includes bibliographical references (pages 70-71).

Rights

© 1962 Cary Chow-Yuen Chen, All rights reserved.

Document Type

Thesis - Open Access

File Type

text

Language

English

Thesis Number

T 1417

Print OCLC #

5948830

Electronic OCLC #

1011528176

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