Nondestructive fissile isotopic measurement technique for /sup 233/U--/sup 235/U fuels using prompt and delayed fission--neutron counting

Technical Report · Thu Mar 01 04:00:00 EST 1979

DOI:https://doi.org/10.2172/6228213· OSTI ID:6228213

Allen, E J; McNeany, S R

Assay and analysis procedures were developed for nondestructive fissile isotopic measurement of mixed /sup 233/U--/sup 235/U fuel samples. For /sup 233/U much fewer delayed neutrons are released per fission than for /sup 235/U, although the number of prompt neutrons is approximately the same. By separately counting prompt and delayed neutrons released by a sample exposed to neutron irradiation, the amounts of /sup 233/U and /sup 235/U present in the sample can be estimated. Equations of delayed- and prompt-neutron counts versus /sup 233/U and /sup 235/U contents are solved simultaneously for the /sup 233/U and /sup 235/U contents of a sample. Eleven samples containing mixtures of /sup 233/U and /sup 235/U from no /sup 233/U to nearly 100% were prepared and assayed in prompt- and delayed-neutron assay devices. Constants for calibration equations, which are derived in this report, were fitted to data from nine of the samples. The maximum differences between counts calculated by the calibration equations and measured counts were 2.3% for delayed neutrons and 1.2% for prompt neutrons, indicating a good selection of the form for the calibration equations. The two remaining samples were treated as unknowns, and the uranium contents of these samples were estimated by simultaneously solving the two calibration equations. The maximum difference between estimated /sup 233/U or /sup 235/U content and actual content for either sample was 1.5%.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6228213
• Report Number(s): ORNL/TM-6686
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CHEMICAL ANALYSIS
DATA
DATA FORMS
DELAYED NEUTRONS
ELEMENTARY PARTICLES
ENERGY SOURCES
EQUATIONS
EVEN-ODD NUCLEI
EXPERIMENTAL DATA
FERMIONS
FISSION
FISSION NEUTRONS
FISSION YIELD
FUELS
GRAPHS
HADRONS
HEAVY NUCLEI
INFORMATION
ISOMERIC TRANSITION ISOTOPES
ISOTOPE RATIO
ISOTOPES
MATERIALS TESTING
MINUTES LIVING RADIOISOTOPES
NEUTRONS
NONDESTRUCTIVE TESTING
NUCLEAR FUELS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
NUCLEONS
NUMERICAL DATA
PROMPT NEUTRONS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
RADIOMETRIC ANALYSIS
REACTOR MATERIALS
TABLES
TESTING
THEORETICAL DATA
URANIUM 233
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
YIELDS