MCNPX-PoliMi for nuclear nonproliferation applications

Pozzi, Sara A.; Clarke, Shaun D.; Walsh, William J.; Miller, Eric K.; Dolan, Jennifer L.; Flaska, Marek; Wieger, Brian M.; Enqvist, Andreas; Padovani, Enrico; Mattingly, John; Chichester, David L.; Puppa, Paolo

doi:10.1016/j.nima.2012.07.040

Cited by 107 publications

(43 citation statements)

References 8 publications

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“…The system was modeled using MCNPX version 2.7.0 and MCNPX-PoliMi version 2.7 to calculate several detection characteristics that included absolute neutron efficiency and the intrinsic die-away constant. [18,19,20] A schematic of this modeled geometry is shown in Figure 4. The Monte Carlo models focused on simulating measurements of a 252 Cf spontaneous fission source that is built into the MCNPX-PoliMi code.…”

Section: Fast Neutron Multiplicity Counter Prototype Designmentioning

confidence: 99%

MPACT Fast Neutron Multiplicity System Prototype Development

Chichester¹,

Pozzi²,

Dolan³

et al. 2013

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This document serves as both an FY2103 End-of-Year and End-of-Project report on efforts that resulted in the design of a prototype fast neutron multiplicity counter leveraged upon the findings of previous project efforts. The prototype design includes 32 liquid scintillator detectors with cubic volumes 7.62 cm in dimension configured into 4 stacked rings of 8 detectors. Detector signal collection for the system is handled with a pair of Struck Innovative Systeme 16-channel digitizers controlled by in-house developed software with built-in multiplicity analysis algorithms. Initial testing and familiarization of the currently obtained prototype components is underway, however full prototype construction is required for further optimization.Monte Carlo models of the prototype system were performed to estimate die-away and efficiency values. Analysis of these models resulted in the development of a software package capable of determining the effects of nearest-neighbor rejection methods for elimination of detector cross talk. A parameter study was performed using previously developed analytical methods for the estimation of assay mass variance for use as a figure-of-merit for system performance. [1, 2] A software package was developed to automate these calculations and ensure accuracy. The results of the parameter study show that the prototype fast neutron multiplicity counter design is very nearly optimized under the restraints of the parameter space.

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Section: Fast Neutron Multiplicity Counter Prototype Designmentioning

confidence: 99%

MPACT Fast Neutron Multiplicity System Prototype Development

Chichester¹,

Pozzi²,

Dolan³

et al. 2013

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show abstract

“…It is important that the physics of particle emission (specifically fission) is as accurate as possible when modeling correlated/multiplicity measurements. [17] MCNPX-PoliMi incorporates neutron and photon multiplicity distributions with correlated neutron and photon production. [15] After the production of all source particles, detailed interaction information is recorded within all volumes of interest.…”

Section: Simulating Multiplicity Systems With Mcnpx-polimi/mppostmentioning

confidence: 99%

MPACT Fast Neutron Multiplicity System Design Concepts

Chichester¹,

Pozzi²,

Dolan³

et al. 2012

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This report documents work performed by Idaho National Laboratory and the University of Michigan in fiscal year (FY) 2012 to examine design parameters related to the use of fast-neutron multiplicity counting for assaying plutonium for materials protection, accountancy, and control purposes. This project seeks to develop a new type of neutron-measurement-based plutonium assay instrument suited for assaying advanced fuel cycle materials. Some current-concept advanced fuels contain high concentrations of plutonium; some of these concept fuels also contain other fissionable actinides besides plutonium. Because of these attributes the neutron emission rates of these new fuels may be much higher, and more difficult to interpret, than measurements made of plutoniumonly materials. Fast neutron multiplicity analysis is one approach for assaying these advanced nuclear fuels.Studies have been performed to assess the conceptual performance capabilities of a fast-neutron multiplicity counter for assaying plutonium. Comparisons have been made to evaluate the potential improvements and benefits of fast-neutron multiplicity analyses versus traditional thermal-neutron counting systems. Fast-neutron instrumentation, using for example an array of liquid scintillators such as EJ-309, have the potential to either a) significantly reduce assay measurement times versus traditional approaches, for comparable measurement precision values, b) significantly improve assay precision values, for measurement durations comparable to current-generation technology, or c) moderately improve both measurement precision and measurement durations versus current-generation technology. Using the MCNPX-PoliMi Monte Carlo simulation code, studies have been performed to assess the doubles-detection efficiency for a variety of counter layouts of cylindrical liquid scintillator detector cells over one, two, and three rows.Ignoring other considerations, the best detector design is the one with the most detecting volume. However, operational limitations guide a) the maximum acceptable size of each detector cell (due to PSD performance and maximum-acceptable per-channel data throughput rates, limited by pulse pile-up and the processing rate of the electronics components of the system) and b)

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“…MCNPX-PoliMi is ideal for designing detection systems, such as fast-neutron-multiplicity counters, due to its: capability of realistically simulating correlated source events, detailed particle interaction output, and incorporation of common SNM sources with accurately sampled energy, number of particles emitted, and their angle distributions [3]. MPPost processes the MCNPX-PoliMi data file into total measurement system response [3]. At UM, the measurement system design process is expedited with the UM parallelized version of MCNPX-PoliMi coupled with UM's advanced computing resources.…”

Section: Simulation and Modeling Tools For Nuclear Safeguards Apmentioning

confidence: 99%

Passive measurement of organic-scintillator neutron signatures for nuclear safeguards applications

Dolan

Miller

Kaplan

et al. 2012

2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC)

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Abstract-At nuclear facilities, domestically and internationally, most measurement systems used for nuclear materials' control and accountability rely on He-3 detectors. Due to resource shortages, alternatives to He-3 systems are needed. This paper presents preliminary simulation and experimental efforts to develop a fast-neutron-multiplicity counter based on liquid organic scintillators. This mission also provides the opportunity to broaden the capabilities of such safeguards measurement systems to improve current neutron-multiplicity techniques and expand the scope to encompass advanced nuclear fuels.

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MCNPX-PoliMi for nuclear nonproliferation applications

Cited by 107 publications

References 8 publications

MPACT Fast Neutron Multiplicity System Prototype Development

MPACT Fast Neutron Multiplicity System Prototype Development

MPACT Fast Neutron Multiplicity System Design Concepts

Passive measurement of organic-scintillator neutron signatures for nuclear safeguards applications

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