Accession Number:

AD0481359

Title:

ABSOLUTE NEUTRON FLUX OF THE AGN-201 REACTOR

Descriptive Note:

Master's thesis

Corporate Author:

NAVAL POSTGRADUATE SCHOOL MONTEREY CA

Personal Author(s):

• Perry, Jr, Roger E.

Report Date:

1964-01-01

Pagination or Media Count:

40.0

Abstract:

Absolute total and thermal neutron flux of the U. S. Naval Postgraduate Schools AGN-201 reactor was determined by neutron activation of thin gold foils. Foil activities were measured with a gamma-ray scintillation spectrometer, using methods designed to minimize the effect of changes in spectrometer gain. Flux values were calculated for nominal power levels of 0.1 watt and 1, 10, 100, and 750 watts. Methods and results are compared with those of previous investigations. The flux level was found to be a linear function of power within this range total and thermal average fluxes were determined to be respectively 6.64 x 10 to the 7th power and 5.41 x 10 to the 7th power neutrons per square centimeter per second per watt.

Descriptors:

• *NEUTRON FLUX
• *RESEARCH REACTORS
• ERRORS
• FOILS(MATERIALS)
• GAMMA RAYS
• GOLD
• INDIUM
• MEASUREMENT
• MONITORS
• NEUTRON ACTIVATION
• NUCLEAR RADIATION SPECTROMETERS
• POWER
• PROBABILITY
• REACTOR CONTROL
• REACTOR LATTICE PARAMETERS
• REACTOR OPERATION
• REACTOR POWER DENSITY
• SCINTILLATION COUNTERS
• STATISTICAL ANALYSIS

Subject Categories:

• Nuclear Fission Reactors (Non-Power)
• Fission Reactor Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE