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Active neutron coincidence counting to determine fissile mass of uranium oxide containing 233U and 235U

Journal Article · · Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment
 [1];  [2];  [2];  [3];  [4]
  1. North Carolina State University, Raleigh, NC (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  3. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
  4. North Carolina State University, Raleigh, NC (United States)
Active neutron coincidence measurements of uranium oxide (UO3) were conducted with an active well coincidence counter (AWCC) at Oak Ridge National Laboratory (ORNL). We performed systematic measurements with the AWCC in fast and thermal mode of well-documented uranium oxide items containing 233U, 235U, and mixtures of the two isotopes up to 144 g of total fissile mass. The objective was to document active neutron coincidence measurements of items containing 233U and to assess the feasibility of 233U characterization and discrimination from 235U using existing neutron-based safeguards instrumentation and measurement methods. The colocation of 233U with other isotopes of uranium, including 235U, presents a challenge because existing nondestructive assay (NDA) methods are not tailored to these isotopic mixtures. Therefore, neutron signatures of 233U-bearing materials were performed and documented to inform the safeguards community when addressing future nuclear nonproliferation needs related to 233U for material control and accountability and potential thorium-based advanced reactors, which breed 233U. The neutron coincidence measurements described contribute to the foundation for future development of material characterization methods and provide experimental data points for validation of simulations. We measured active calibration curves, which relate the fissile mass to the coincident count rate, for 2–80 g of 233U, 2–64 g235U, and 4–144 g of a mixture of 233U and 235U. In thermal mode, the total fissile mass could be determined, but isotope discrimination is not possible. An unknown mixed item was measured in thermal mode and the total fissile mass was calculated within 1σ of the declared mass. In fast mode, we observe a difference between the 233U and 235U curves, but a low coincidence count rate and high uncertainty prevent statistically meaningful determination of fissile mass, especially for 235U.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
Grant/Contract Number:
89233218CNA000001
OSTI ID:
2506856
Alternate ID(s):
OSTI ID: 2507000
Report Number(s):
LA-UR--24-26797
Journal Information:
Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment, Journal Name: Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment Vol. 1072; ISSN 0168-9002
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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