Determination of uranium-235 by a delayed neutron counting technique
Technical Report
·
OSTI ID:4399688
Annual progress report for the period July 1972 through June Determination of /sup 235/U in uranium dioxide-- thorium dioxide mixtures and pyrocarbon- and silicon carbide-coated uranium-- thorium carbide fuel beads was carried out by bombarding with thermal neutrons and counting the delayed neutrons arising from fission of the /sup 235/U. The precision and accuracy of some results are given. (auth)
- Research Organization:
- USAEC New Brunswick Lab., N.J.
- NSA Number:
- NSA-29-000089
- OSTI ID:
- 4399688
- Report Number(s):
- NBL--267
- Country of Publication:
- United States
- Language:
- English
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· Nucl. Technol.; (United States)
·
OSTI ID:5487112
Related Subjects
*THORIUM CARBIDES-- CHEMICAL ANALYSIS
*THORIUM OXIDES-- CHEMICAL ANALYSIS
*URANIUM 235-- NUCLEAR REACTION ANALYSIS
*URANIUM CARBIDES-- CHEMICAL ANALYSIS
*URANIUM DIOXIDE-- CHEMICAL ANALYSIS
FISSION
N40130* --Chemistry--Analytical & Separations Chemistry-- Radiometric & Radiochemical Procedures
NUCLEAR FUELS
QUANTITATIVE CHEMICAL ANALYSIS
THERMAL NEUTRONS
*THORIUM OXIDES-- CHEMICAL ANALYSIS
*URANIUM 235-- NUCLEAR REACTION ANALYSIS
*URANIUM CARBIDES-- CHEMICAL ANALYSIS
*URANIUM DIOXIDE-- CHEMICAL ANALYSIS
FISSION
N40130* --Chemistry--Analytical & Separations Chemistry-- Radiometric & Radiochemical Procedures
NUCLEAR FUELS
QUANTITATIVE CHEMICAL ANALYSIS
THERMAL NEUTRONS