Abstract
We describe a generalized means of isotopic assay and quantification of multicomponent fissile mixtures based on the observation of short-lived fission-product gamma signatures. Given that the characteristic mass yield curves differ for individual fissile species, this can be used to construct an overdetermined system of equations corresponding to the observed photopeak yields, the solution of which yields information on the individual isotopic masses of parent fissile isotopes within the system. This method is then demonstrated for single-isotope samples of 233U, 235U, and 239Pu; binary fissile mixtures of U and Pu; and trace fissile samples contained within intact typical environmental sampling media, each irradiated and measured using the High Flux Isotope Reactor at the Oak Ridge National Laboratory. Our findings indicate that this method can reliably be used to quantify nanogram-level fissile masses in binary mixtures with uncertainties on the order of 2%-7%. Finally, observed discrepancies with individual fission-product indicators and likely sources of bias are discussed.
Original language | English |
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Article number | 8794604 |
Pages (from-to) | 2123-2135 |
Number of pages | 13 |
Journal | IEEE Transactions on Nuclear Science |
Volume | 66 |
Issue number | 9 |
DOIs | |
State | Published - 2019 |
Funding
Manuscript received February 18, 2019; revised July 5, 2019 and July 10, 2019; accepted August 8, 2019. Date of publication August 12, 2019; date of current version September 16, 2019. This work was supported in part by the Bredesen Center for Interdisciplinary Research and Graduate Education, University of Tennessee at Knoxville, and in part by the Oak Ridge National Laboratory, University of Tennessee at Battelle, LLC, through the U.S. Department of Energy under Contract DE-AC05-00OR22725.
Funders | Funder number |
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Bredesen Center for Interdisciplinary Research and Graduate Education, University of Tennessee at Knoxville | |
University of Tennessee at Battelle | |
U.S. Department of Energy | DE-AC05-00OR22725 |
Oak Ridge National Laboratory |
Keywords
- Delayed gamma
- High Flux Isotope Reactor (HFIR)
- Origen
- neutron activation analysis (NAA)
- nondestructive assay (NDA)
- nuclear forensics
- safeguards
- short-lived fission products