Nondestructive fissile isotopic measurement technique for /sup 233/U--/sup 235/U fuels using prompt and delayed fission--neutron counting
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. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6228213
- Report Number(s):
- ORNL/TM-6686
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
DELAYED NEUTRONS
FISSION YIELD
NUCLEAR FUELS
ISOTOPE RATIO
RADIOMETRIC ANALYSIS
PROMPT NEUTRONS
URANIUM 233
FISSION
URANIUM 235
EQUATIONS
EXPERIMENTAL DATA
GRAPHS
NONDESTRUCTIVE TESTING
TABLES
THEORETICAL DATA
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CHEMICAL ANALYSIS
DATA
DATA FORMS
ELEMENTARY PARTICLES
ENERGY SOURCES
EVEN-ODD NUCLEI
FERMIONS
FISSION NEUTRONS
FUELS
HADRONS
HEAVY NUCLEI
INFORMATION
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATERIALS TESTING
MINUTES LIVING RADIOISOTOPES
NEUTRONS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
NUCLEONS
NUMERICAL DATA
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
REACTOR MATERIALS
TESTING
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
YIELDS
050700* - Nuclear Fuels- Fuels Production & Properties