COMPARATIVE THERMAL FLUX DISTRIBUTIONS, Mn VS. U$sup 235$ DETECTORS
Technical Report
·
OSTI ID:4295511
An experiment was performed on a water-reflected slab reactor with central water channel to determine whether a thermal flux traverse as measured with manganese detectors differs from that obtained with U/sup 235/ detectors. The flux distribution was determined across the narrow dimension of the core by measuring the induced beta-ray activity in Manganin wire, and by measuring the beta activity of the fission products produced by irradiation of U/sup 235/--Zr wire. Epi-cadmium flux was measured by the irradiation of wires covered with 0.016 in. thick cadmium tubing. (W.D.M.)
- Research Organization:
- Westinghouse Electric Corp. Bettis Plant, Pittsburgh
- NSA Number:
- NSA-13-000737
- OSTI ID:
- 4295511
- Report Number(s):
- WAPD-PWR-Ph-146(Del.)
- Country of Publication:
- United States
- Language:
- English
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Mon Jan 22 23:00:00 EST 1962
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Instrumental neutron activation analysis in the determination of the $sup 235$U/$sup 238$U isotopic ratios for samples from 0.4 to 93% $sup 235$U
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Related Subjects
ACTIVATION
BETA PARTICLES
CADMIUM
COATING
CONFIGURATION
COPPER ALLOYS
DISTRIBUTION
FISSION PRODUCTS
INSTRUMENTS
IRRADIATION
MANGANESE
MANGANESE ALLOYS
MANGANIN
MEASURED VALUES
NEUTRON DETECTION
NEUTRON FLUX
RADIATION DETECTORS
RADIOACTIVITY
REACTOR CORE
REACTORS
STANDARDS
THERMAL NEUTRONS
THICKNESS
TUBES
URANIUM 235
WATER MODERATOR
WIRES
ZIRCONIUM
BETA PARTICLES
CADMIUM
COATING
CONFIGURATION
COPPER ALLOYS
DISTRIBUTION
FISSION PRODUCTS
INSTRUMENTS
IRRADIATION
MANGANESE
MANGANESE ALLOYS
MANGANIN
MEASURED VALUES
NEUTRON DETECTION
NEUTRON FLUX
RADIATION DETECTORS
RADIOACTIVITY
REACTOR CORE
REACTORS
STANDARDS
THERMAL NEUTRONS
THICKNESS
TUBES
URANIUM 235
WATER MODERATOR
WIRES
ZIRCONIUM