Analysis of response data for several organic scintillators

Craun, R.L.; Smith, D.L.

doi:10.1016/0029-554x(70)90768-8

Cited by 254 publications

(91 citation statements)

References 15 publications

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“…Since this investigation aimed at the question of the effectiveness of passive converters, a relative measurement was sufficient. The absolute detection efficiencies of plastic scintillator materials have been measured many times and can be calculated with good accuracy [3,4].…”

Section: Resultsmentioning

confidence: 99%

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Improving neutron detection efficiency by using passive converters

Baumann

Ikeda

Kurokawa

et al. 2002

Nuclear Instruments and Methods in Physics Research Section B:

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Section: Resultsmentioning

confidence: 99%

“…While the parameters of the simulation could be adjusted to match experimental data for plastic scintillators [3,4], the question of how well the simulation described a converter-scintillator combination in the energy region of interest remained open. Now we are able to compare the predictions of our simulation with the measured data.…”

Section: Simulationmentioning

confidence: 99%

Improving neutron detection efficiency by using passive converters

Baumann

Ikeda

Kurokawa

et al. 2002

Nuclear Instruments and Methods in Physics Research Section B:

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“…The formulas provide reasonable representations of the data sets in Craun and Smith (1970), which span the energy range from about 400 keV to 1 MeV (gamma) and 300 keV to 10 MeV (proton). According to the electron response formula, a threshold of 70 keV in the 137 Cs source case corresponds to a light output response R e of about 48 units.…”

Section:  mentioning

confidence: 98%

“…Note that this threshold is a factor of 5 higher than the 137 Cs gamma-response threshold of 70 keV derived from a similar comparison of the graphs plotted in Figure 3 This energy deposition threshold difference is not surprising because the light output of plastic scintillator when subjected to energy deposition by heavy ionizing particles (e.g., protons and 12 C ions, the main recoil products of elastic neutron scattering in plastic scintillator) is markedly smaller than the light response produced by fast electrons (i.e., the secondary products of gamma interactions) depositing the same amount of energy. The relative (electron, proton) light output responses of NE102 plastic scintillator (essentially identical to the BC-408 scintillator used in the n-TOF sensor) can be derived from measurements reported in Craun and Smith (1970) …”

Section: Cf Neutron Sourcementioning

confidence: 99%

Methods and Instruments for Fast Neutron Detection

Jordan¹,

Reeder²,

Cooper³

et al. 2005

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Pacific Northwest National Laboratory evaluated the performance of a large-area (~0.7 m 2 ) plastic scintillator time-of-flight (TOF) sensor for direct detection of fast neutrons. This type of sensor is a readily area-scalable technology that provides broad-area geometrical coverage at a reasonably low cost. It can yield intrinsic detection efficiencies that compare favorably with moderator-based detection methods. The timing resolution achievable should permit substantially more precise time windowing of return neutron flux than would otherwise be possible with moderated detectors. The energy-deposition threshold imposed on each scintillator contributing to the event-definition trigger in a TOF system can be set to blind the sensor to direct emission from the neutron generator. The primary technical challenge addressed in the project was to understand the capabilities of a neutron TOF sensor in the limit of large scintillator area and small scintillator separation, a size regime in which the neutral particle's flight path between the two scintillators is not tightly constrained.The project comprised an experimental campaign and a modeling campaign. The experimental campaign focused on measuring the response of an existing, dual-sheet scintillator sensor to mono-energetic gamma sources (including 137 Cs and 54 Mn) and a 252 Cf gamma + neutron source. The sensor's intrinsic gamma and neutron detection efficiencies were mapped as a function of the TOF threshold above which the sensor's response is integrated. A fast neutron intrinsic detection efficiency of approximately 2.5%, averaged over the 252 Cf neutron spectrum, was obtained at a TOF threshold that permits approximately 10,000:1 gamma rejection. An additional contribution to the sensor's total intrinsic neutron detection efficiency of roughly 1.3% results from including the TOF response to neutron flux reflected from a 5.08 cm (2 in.) layer of Pb shielding surrounding the sensor on four sides. In addition to the TOF measurements, the report presents preliminary investigations of the supplementary neutron spectroscopic information content available in scintillator pulse-height measurements.The modeling campaign consisted of development of a simulation code based upon the Geant4 radiation transport framework. A prescription for calculating effective particle interaction times in each scintillator of the TOF sensor is described. This prescription avoids the significant computational overhead associated with tracking large ensembles of scintillation photons, at the cost of sacrificing a realistic model of the sensor's photomultiplier tube (PMT) signal pulse development with time. The model predicts the qualitative features of the neutron TOF distribution (although it underpredicts the Pbreflected component) and provides a consistent description of the measured neutron and gamma detection efficiencies. The model fails to predict the shapes of the gamma and neutron responses accurately enough to permit reliable prediction of the details of the gamma reje...

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“…response function [44,45,46]. The method is based upon the concept that the quenching of light stems from recombination of electrons and ions in the scintillator.…”

Section: Energy Reconstruction and Responsementioning

confidence: 99%

Fast neutron detection with a segmented spectrometer

Langford

Bass

Beise

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

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A fast neutron spectrometer consisting of segmented plastic scintillator and 3 He proportional counters was constructed for the measurement of neutrons in the energy range 1 MeV to 200 MeV. We discuss its design, principles of operation, and the method of analysis. The detector is capable of observing very low neutron fluxes in the presence of ambient gamma background and does not require scintillator pulse-shape discrimination. The spectrometer was characterized for its energy response in fast neutron fields of 2.5 MeV, 14 MeV, and the results are compared with Monte Carlo simulations. Measurements of the fast neutron flux and energy response at 120 m above sea-level (39.130 • N, 77.218• W) and at a depth of 560 m in a limestone mine are presented. Finally, the design of a spectrometer with improved sensitivity and energy resolution is discussed.

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Analysis of response data for several organic scintillators

Cited by 254 publications

References 15 publications

Improving neutron detection efficiency by using passive converters

Improving neutron detection efficiency by using passive converters

Methods and Instruments for Fast Neutron Detection

Fast neutron detection with a segmented spectrometer

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