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Correlations in Prompt Neutrons and Gamma Rays from Fission
S. A. Pozzi1, M. J. Marcath1, T. H. Shin1, Angela Di Fulvio1 , S. D. Clarke1, E. W. Larsen1,
R. Vogt2,3, J. Randrup4, R. C. Haight5, P. Talou5, T. Kawano5, I. Stetcu5, E. Padovani6
1Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI, USA 2Lawrence Livermore National Laboratory, Livermore, CA, USA 3University of California, Davis, CA, USA 4Lawrence Berkeley National Laboratory, Berkeley, CA, USA 5Los Alamos National Laboratory, Los Alamos, NM, USA 6Department of Energy, Polytechnic of Milan, Milan, Italy
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
Motivation
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• Nuclear nonproliferation and safeguards applications require improved models for physics of nuclear fission and detector response.
• Specifically, the correlated neutron and gamma ray emission properties of important nuclear isotopes such as 235U and 239Pu are not well known. These data are important in nuclear safeguards and nonproliferation.
• The present work builds on that experience and includes correlated information.
• There is a need for a new set of measured data to compare to fission models.
• Key neutron and gamma ray quantities to measure – Detected multiplicity
– Energy spectra
– Relative angle of emission
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
• Neutrons emitted in the direction of motion of the fission fragment (FF) have the FF momentum added to their energy
Nuclear Fission
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Center of Mass Frame Lab Frame
Direction of motion
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
Nuclear Fission Modeling MCNPX-PoliMi
• The multiple variables associated with nuclear fission are sampled independently by most Monte Carlo codes.
• MCNPX-PoliMi spontaneous fission model samples neutrons and gamma rays from a full multiplicity distribution.
• Neutron multiplicity dependent energy spectra.
• Anisotropic neutron angular distribution.
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0 1 2 3 4 5 6 7 8 90
0.05
0.1
0.15
0.2
0.25
0.3
0.35
Neutrons Emitted
Pro
ba
bili
ty
Pu-240
Cf-252
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
Nuclear Fission Modeling CGMF and FREYA
• Theoretical research is underway to develop CGMF and FREYA models that exhibit fission-particle correlations.
• CGMF and FREYA are event-by-event Monte Carlo codes that follow the fission event from scission to de-excitation
• Active collaboration is underway to verify these models and PoliMi with measured data.
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
UMich and LANL ChiNu Array Cf-252 Experiments
• EJ-309 organic liquid scintillator
– 17.78Ø×5.08 cm active volume
– 12.7 cm Hamamatsu R4144
– 1.25 H:C
– 0.94 g/cm3
• Pulse shape discrimination capable
MCNPX-PoliMi simulated 17.78Ø×5.08 cm EJ-309 40 keVee threshold =~0.5 MeV deposition
17.78Ø×5.08 cm EJ-309
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
UMich Cf-252 Experiment
• In the Fall of 2014, an inorganic and organic scintillator array sensitive to both gamma-ray and neutrons has been created to investigate Cf-252 spontaneous fission gamma-ray and neutron correlations.
• This array provides a range of correlated measureables – Time cross-correlation distributions – Detected neutron and detected
gamma-ray multiplicities – Neutron energy from photon TOF as
a function of the number of detected photons
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
LANL ChiNu Array Cf-252 Experiment
• In the summer of 2015, a
measurement was made of neutrons and gamma rays from a Cf-252 fission chamber with the LANL ChiNu liquid organic scintillator array – Larger source-detector
distance of 1 m – factor 2
– Stronger source – factor 8
– Fission chamber – better timing resolution and trigger
– Larger solid angle coverage – factor 2
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ORNL designed Cf-252 fission chamber
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
LANL ChiNu Array Cf-252 Experiment
• 3,000 cps/detector
• 125 MB/s
• 30 hours and 27 billion fissions later we have 13 TB of waveforms
• Post-processing time is significant
• Physical storage space becomes difficult with full waveforms
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
LANL ChiNu Array Cf-252 Experiment
Results for a time cross-correlation distribution between pair of EJ-309s
Pairs of EJ-309s
Count rate as a function of angle between detectors
• Double coincidences are analyzed, but higher order coincidences are the target measurable
• Constructing a detailed MCNPX model for fission model comparison
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
UMich and LANL ChiNu Array Cf-252 Experiments Neutron Cross-Talk Characterization
• Scatter-based non-absorbing detectors are prone to neutron cross-talk – A single neutron can scatter into one or
more detectors subsequently registering multiple counts
– Adversely increases correlated counts
• Characterization of cross-talk and its effect on the total observed coincidence counts is significant when experimental systems utilize numerous detectors
• Need to measure isolated cross-talk neutrons from Cf-252 spontaneous fission source and validate MCNPX-PoliMi simulations
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Detector 3
Θ
1m
1m
Cf-252
Detector 1 t1
Detector 2 t2
Po
lyet
hyle
ne,
60 c
m
Detector-source-
detector angle
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
UMich and LANL ChiNu Array Cf-252 Experiments Neutron Cross-Talk Characterization
• Time cross-correlation distributions were compared to MCNPX-PoliMi simulations and show good agreement.
• Neutron cross-talk counts within a measurement system primarily dependent on:
– Detector-source-detector angle
– Detector-detector distance
– Detector light output threshold
• Relative effects of neutron cross-talk characterized by these parameters, see poster this afternoon.
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Detector-Source-Detector Angle Θ 10° 20° 30°
Measured Integrated Count Rate [counts/sec]
2.798 0.6954 0.3301
MCNPX-PoliMi Integrated Count Rate [counts/sec]
3.213 0.7313 0.3561
% Difference 12.91 % 4.901 % 7.292 %
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
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Future Work Induced-Fission Measurements at WNR Facility at LANSCE
WNR - fast
neutron source
Lujan center –
moderated
neutron source
Ultracold neutron source
Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
Summary and Conclusions
• Measurements of correlated, prompt emissions from 252Cf have been performed and partially analyzed
• There is a need for a measured correlated-data set to compare with fission model simulations
• Accurate models are necessary in order to effectively design such systems
• Advanced verification system could rely on detailed correlated emissions from fission
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Consortium for Verification Technology: Workshop - October 15th & 16th, 2015
Acknowledgements
• Thanks to my mentors at LANL Robert Haight, Matthew Devlin, and Patrick Talou.
• This research was performed under appointment to the U.S. Department of Energy Nuclear Nonproliferation International Safeguards Graduate Fellowship Program sponsored by the National Nuclear Security Administration’s Office of Nonproliferation and International Security.
• This work was funded in-part by the Consortium for Verification Technology under Department of Energy National Nuclear Security Administration award number DE-NA0002534.
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Correlations in Prompt Neutrons and Gamma Rays from Fission S. A. Pozzi1, M. J. Marcath1, T. H. Shin1, Angela Di Fulvio1 , S. D. Clarke1, E. W. Larsen1,
R. Vogt2,3, J. Randrup4, R. C. Haight5, P. Talou5, T. Kawano5, I. Stetcu5, E. Padovani6
1Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI, USA 2Lawrence Livermore National Laboratory, Livermore, CA, USA 3University of California, Davis, CA, USA 4Lawrence Berkeley National Laboratory, Berkeley, CA, USA 5Los Alamos National Laboratory, Los Alamos, NM, USA 6Department of Energy, Polytechnic of Milan, Milan, Italy