Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response
Abstract
Apparatus and method for the direct, nondestructive evaluation of the /sup 235/U nuclide content of samples containing UF/sub 6/, UF/sub 4/, or UO/sub 2/ utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1sigma) for cylinders containing UF/sub 6/ with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF/sub 6/ takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures. 4 figs., 1 tab.
- Inventors:
- Issue Date:
- Research Org.:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- OSTI Identifier:
- 5320785
- Application Number:
- ON: DE85017794
- Assignee:
- Dept. of Energy
- DOE Contract Number:
- W-7405-ENG-36
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; URANIUM 235; RADIOMETRIC ANALYSIS; URANIUM DIOXIDE; QUANTITATIVE CHEMICAL ANALYSIS; URANIUM HEXAFLUORIDE; ACCURACY; ALPHA DECAY; ALPHA REACTIONS; COINCIDENCE METHODS; EXPERIMENTAL DATA; NEUTRON DETECTION; SAFEGUARDS; SPONTANEOUS FISSION; ACTINIDE COMPOUNDS; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; CHARGED-PARTICLE REACTIONS; CHEMICAL ANALYSIS; COUNTING TECHNIQUES; DATA; DECAY; DETECTION; EVEN-ODD NUCLEI; FISSION; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HEAVY NUCLEI; INFORMATION; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NUCLEAR REACTIONS; NUCLEI; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; RADIATION DETECTION; RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM FLUORIDES; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES; 400103* - Radiometric & Radiochemical Procedures- (-1987); 055001 - Nuclear Fuels- Safeguards, Inspection, & Accountability- Technical Aspects
Citation Formats
Menlove, H O, and Stewart, J E. Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response. United States: N. p., 1985.
Web.
Menlove, H O, & Stewart, J E. Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response. United States.
Menlove, H O, and Stewart, J E. Mon .
"Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response". United States.
@article{osti_5320785,
title = {Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response},
author = {Menlove, H O and Stewart, J E},
abstractNote = {Apparatus and method for the direct, nondestructive evaluation of the /sup 235/U nuclide content of samples containing UF/sub 6/, UF/sub 4/, or UO/sub 2/ utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1sigma) for cylinders containing UF/sub 6/ with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF/sub 6/ takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures. 4 figs., 1 tab.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1985},
month = {2}
}