TY - JOUR
T1 - Passive measurements of mixed-oxide fuel for nuclear nonproliferation
AU - Dolan, Jennifer L.
AU - Flaska, Marek
AU - Pozzi, Sara A.
AU - Chichester, David L.
N1 - Funding Information:
This work was supported by the US Department of Energy's Fuel Cycle Technologies Program , in the Material Protection, Accounting, and Control Technologies (MPACT) Campaign. Idaho National Laboratory is operated for the US Department of Energy by Battelle Energy Alliance under DOE contract DE-AC07-05-ID14517 . This work was also supported by the National Science Foundation and the Domestic Nuclear Detection Office of the Department of Homeland Security through the Academic Research Initiative Award ♯ CMMI 0938909 . This research was performed under the Nuclear Forensics Graduate Fellowship Program which is sponsored by the US Department of Homeland Security's Domestic Nuclear Detection Office and the US Department of Defense's Defense Threat Reduction Agency.
PY - 2013
Y1 - 2013
N2 - We present new results on passive measurements and simulations of mixed-oxide fuel-pin assemblies. Potential tools for mixed-oxide fuel pin characterization are discussed for future nuclear-nonproliferation applications. Four EJ-309 liquid scintillation detectors coupled with an accurate pulse timing and digital, offline and optimized pulse-shape discrimination method were used. Measurement analysis included pulse-height distributions to distinguish between purely fission neutron sources and alpha-n plus fission neutrons sources. Time-dependent cross-correlation functions were analyzed to measure the fission neutron contribution to the measured sample's neutron source. The use of Monte Carlo particle transport code MCNPX-PoliMi is discussed in conjunction with the measurements.
AB - We present new results on passive measurements and simulations of mixed-oxide fuel-pin assemblies. Potential tools for mixed-oxide fuel pin characterization are discussed for future nuclear-nonproliferation applications. Four EJ-309 liquid scintillation detectors coupled with an accurate pulse timing and digital, offline and optimized pulse-shape discrimination method were used. Measurement analysis included pulse-height distributions to distinguish between purely fission neutron sources and alpha-n plus fission neutrons sources. Time-dependent cross-correlation functions were analyzed to measure the fission neutron contribution to the measured sample's neutron source. The use of Monte Carlo particle transport code MCNPX-PoliMi is discussed in conjunction with the measurements.
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U2 - 10.1016/j.nima.2012.11.092
DO - 10.1016/j.nima.2012.11.092
M3 - Article
AN - SCOPUS:84871164204
SN - 0168-9002
VL - 703
SP - 102
EP - 108
JO - Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
JF - Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
ER -