Nondestructive fissile isotopic measurement technique for Uranium-233 - Uranium-235 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, the number of delayed neutrons released per fission is about half that 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 determined. 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 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 unknown, and the uranium contents of these samples were determined by simultaneously solving the two calibration equations. The maximum difference between measured /sup 233/U or /sup 235/U content and actual content for either sample was 1.%.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 5487112
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 47:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nondestructive assay technique for /sup 233/U and /sup 235/U in mixed samples
Related Subjects
Inspection
& Accountability-- Technical Aspects
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400101* -- Activation
Nuclear Reaction
Radiometric & Radiochemical Procedures
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CHEMICAL ANALYSIS
DELAYED NEUTRON ANALYSIS
ELEMENTARY PARTICLES
EVEN-ODD NUCLEI
FERMIONS
FISSILE MATERIALS
FISSION NEUTRONS
FISSIONABLE MATERIALS
HADRONS
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
NEUTRONS
NONDESTRUCTIVE ANALYSIS
NUCLEAR REACTION ANALYSIS
NUCLEI
NUCLEONS
PROMPT NEUTRONS
RADIOISOTOPES
URANIUM 233
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES