A comparison of untagged gamma-ray and tagged-neutron yields from 241 AmBe and 238 PuBe sources

Scherzinger, J.; Jebali, R. Al; Annand, J. R. M.; Fissum, Kevin; Hall-Wilton, R.; Koufigar, Sharareh; Mauritzson, N.; Messi, F.; Perrey, H.; Rofors, E.

doi:10.1016/j.apradiso.2017.05.014

Cited by 28 publications

(22 citation statements)

References 10 publications

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“…3 He and 4 He, respectively. The elastic scattering cross-section of 4 He exhibits a peak at around 1 MeV, matching the emission spectrum of fission neutrons quite well [43].…”

Section: Objectivesupporting

confidence: 60%

“…When moving the source, the differences in Δt are relatively small, since only one neutron's travel time varies with the change in distance. In addition, gamma rays have higher yield and energy for the Pu-Be source than 252 Cf [43] [44], and are more likely to be misclassified as neutrons due to pile-up and other factors. Therefore, slight nonlinearity is observed as on the right of Figure 53.…”

Section: Cross-correlation Functions With Pu-be (α N) Sourcementioning

confidence: 99%

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Used Fuel Storage Monitoring Using Helium-4 Scintillation Fast Neutron Detectors and Neutron Spectral Analysis

Enqvist

2019

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Major project objectives Objective 1: Create a neutron spectrometer using helium-4 detectors through an experimentally validated neutron energy response function and spectral unfolding techniques. Objective 2: Leverage test measurements and a computation library of spent fuel, enabling the analytical design of a cask-measuring prototype system. Objective 3: Construct a prototype instrument and use it to measure spent fuel casks at a commercial spent fuel storage facility. Objective 4: Develop the capability of cask imaging through a combination of neutron and gamma measurements. Milestones A set of 12 individual milestones was identified at the start of the project and used as a guiding mechanism for different parts of the work under the project. PROJECT MILESTONES # Elements and milestones 1 Determine detector response function by time-of-flight experiment 2 Develop and validate simulation models for 4 He detector 3 Measure detector scintillation signals for various neutron sources in lab environment 4 Investigate and implement pulse shape discrimination and spectrum unfolding algorithms 5 Characterize SiPM-based 4 He detector 6 Develop and validate SiPM-based 4 He detector simulation models 7 Build spent fuel models and spent fuel inventory database 8 Identify measurable emission signatures from spent fuel cask by 4 He detector 9 Investigate signatures from gamma-rays and incorporate gamma-ray detection system 10 Construct a physical prototype detection system for in-service spent fuel monitoring scenario 11 Develop front and back ends of data analysis software package for 4 He detector system 12 Benchmark the detector system prototype at a commercial spent fuel storage facility − + + → *. (4) These excitations will lead to the production of singlet (more probable) or triplet (much less probable) excimer states [45]. The decay of these excimers to the ground state is an important step to produce scintillation photons, which are either shifted in spectrum through wavelength shifting interactions, or directly detected by photomultiplier tubes (PMTs) at either end, as shown in Error! Reference source not found.. The next chapter covers additional details about this scintillation process.

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“…3 He and 4 He, respectively. The elastic scattering cross-section of 4 He exhibits a peak at around 1 MeV, matching the emission spectrum of fission neutrons quite well [43].…”

Section: Objectivesupporting

confidence: 60%

Section: Cross-correlation Functions With Pu-be (α N) Sourcementioning

confidence: 99%

Used Fuel Storage Monitoring Using Helium-4 Scintillation Fast Neutron Detectors and Neutron Spectral Analysis

Enqvist

2019

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“…To understand the degree of neutron to gamma discrimination, the beam monitors were tested using neutron and gamma sources at the Source Testing Facility, Lund University. The used neutron source is Be-based which emits neutrons up to about 11MeV with a maximum intensity in the 3-5 MeV range [26]. In order to thermalize the emitted neutrons, the source is placed in a moderator made of polyethylene.…”

Section: Measurements Methodsmentioning

confidence: 99%

Characterization of thermal neutron beam monitors

Issa

Khaplanov

Hall-Wilton

et al. 2017

Phys. Rev. Accel. Beams

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Neutron beam monitors with high efficiency, low gamma sensitivity, high time and space resolution are required in neutron beam experiments to continuously diagnose the delivered beam. In this work, commercially available neutron beam monitors have been characterized using the R2D2 beamline at IFE (Norway) and using a Be-based neutron source. For the gamma sensitivity measurements different gamma sources have been used. The evaluation of the monitors includes, the study of their efficiency, attenuation, scattering and sensitivity to gamma. In this work we report the results of this characterization.

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“…In particular, an approximate neutron energy spectrum of a 238 Pu/Be source is used as input (see figure 9). It is modelled using several Gaussian distributions, referring to the work on the characterization of the 238 Pu/Be and 241 Am/Be source [25]. The implemented detector geometry and the source placement match the experimental setup and are depicted in figure 10.…”

Section: Geantsimulationsmentioning

confidence: 99%

Fast neutron sensitivity of neutron detectors based on Boron-10 converter layers

et al. 2018

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In the last few years many detector technologies for thermal neutron detection have been developed in order to face the shortage of 3 He, which is now much less available and more expensive. Moreover the 3 He-based detectors can not fulfil the requirements in performance, e.g. the spatial resolution and the counting rate capability needed for the new instruments. The Boron-10-based gaseous detectors have been proposed as a suitable choice. This and other alternatives technologies are being developed at ESS. Higher intensities mean higher signals but higher background as well. The signal-to-background ratio is an important feature to study, in particular the γ-ray and the fast neutron contributions. This paper investigates, for the first time, the fast neutrons sensitivity of 10 B-based thermal neutron detector. It presents the study of the detector response as a function of energy threshold and the underlying physical mechanisms. The latter are explained with the help of theoretical considerations and simulations.

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A comparison of untagged gamma-ray and tagged-neutron yields from 241 AmBe and 238 PuBe sources

Cited by 28 publications

References 10 publications

Used Fuel Storage Monitoring Using Helium-4 Scintillation Fast Neutron Detectors and Neutron Spectral Analysis

Used Fuel Storage Monitoring Using Helium-4 Scintillation Fast Neutron Detectors and Neutron Spectral Analysis

Characterization of thermal neutron beam monitors

Fast neutron sensitivity of neutron detectors based on Boron-10 converter layers

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