Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors

Guardiola, Consuelo; Amgarou, K.; García, F.; Fleta, C.; Quirion, D.; Lozano, M.

doi:10.1088/1748-0221/6/09/t09001

Cited by 23 publications

(23 citation statements)

References 17 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…As would be expected, with the lowest cross section of the three loading elements, lithium, has the lowest capture efficiency. As has previously been observed [18] there is a difference of around 5 % between MCNP and Geant4 in terms of neutron capture efficiency. Although the absolute efficiencies are observed to be different between the two codes, it can be seen that there is a good agreement between the two codes in terms of the trend for neutron capture efficiency against energy, for each scintillator simulated.…”

Section: Resultssupporting

confidence: 70%

“…However the detectors that were modelled were concerned with proton recoil energy and did not use loaded scintillators for neutron capture. At lower neutron energies for thermal neutron simulations, there are conflicting results when compared to simulations performed with MCNP [18]. However, no further results have been published since Geant4 v4.9.2.…”

Section: Establishing a Suitable Model Of The Detectormentioning

confidence: 99%

“…Each of the scintillators were given a density of 0.92 g/cm 3 . Differences in neutron capture efficiency have previously been noted between MCNP and Geant4 simulations [18]. It was decided, for neutron capture efficiency simulations, to use both codes to ensure that the general trend was the same between the two codes.…”

Section: Simulation Parametersmentioning

confidence: 99%

See 2 more Smart Citations

An investigation into a suitable scintillator for localising neutron capture within a detector

2014

View full text Add to dashboard Cite

Using Monte-Carlo modelling, an investigation into a suitable loaded scintillator for localising neutron capture in a novel neutron survey meter has been undertaken. A comparison of estimated neutron capture location in a scintillator with Geant4 and MCNP simulations was undertaken and a good general agreement between the two models was observed. The interactions of γ emissions from neutron capture in the scintillator are investigated. The results show that the γ emission from neutron capture will not aid neutron capture localisation and will only inhibit it. It is observed that the lithium-loaded scintillator has the lowest neutron capture efficiency when compared with boron and gadolinium scintillators. However, it is the most promising of the detectors investigated in this research for use in a novel neutron survey meter design.

show abstract

Section: Resultssupporting

confidence: 70%

Section: Establishing a Suitable Model Of The Detectormentioning

confidence: 99%

See 1 more Smart Citation

An investigation into a suitable scintillator for localising neutron capture within a detector

2014

View full text Add to dashboard Cite

show abstract

“…The particles emitted are charged fragments of high energy loss by dense ionization, thus converter layers have to be as thin as micrometers. Meanwhile these systems are understood and optimized by means of analytical modeling [16] or Monte Carlo transport simulations [17], detailed descriptions for specific geometries can also be found in [18] and [19]. For now a simple single layer as shown in Fig.…”

Section: E-fieldmentioning

confidence: 99%

Novel neutron detectors based on the time projection method

Köhli

Desch

Gruber

et al. 2018

Physica B: Condensed Matter

View full text Add to dashboard Cite

We present the first prototype of a novel thermal neutron detector using the time projection method. The system consists of 8 TimePix ASICS with postprocessed InGrid meshes. Each ASIC has 256 × 256 pixels of 55 µm×55 µm in size with the capability to measure charge or time. This allows to visualize entire conversion particle tracks with their spatial and time information and, by using event reconstruction algorithms, discriminate against the background of others. By using the Scalable Readout System the detector as presented here could also be upscaled to much larger active areas. In the current configuration we could achieve a spatial resolution of σ = (115 ± 8) µm.

show abstract

“…The maximum difference between MCNP6.1.0 and Geant4.10.2 simulations for the four scintillators is less than 5%. These differences are mainly due to differences in cross sections libraries used by MCNP6.1.0 and Geant4.10.2 [46][47][48][49][50]. Table 3.1 compares thermal neutron capture efficiency of the four scintillators at a thickness of 2 cm, 5cm and 10 cm respectively.…”

Section: Thermal Neutronsmentioning

confidence: 99%

Material optimization in dual particle detectors by comparing advanced scintillating materials using two Monte Carlo codes

Hamrashdi¹,

Cheneler²,

Monk³

2017

Nuclear Instruments and Methods in Physics Research Section A:

View full text Add to dashboard Cite

A new generation of scintillating materials have been recently developed in the radiation-imaging field offering very promising dual particle detection abilities. Here, four different scintillating materials (Cs2LiYCl6:Ce (CLYC), 95% 6 Li enriched Cs2LiYCl6:Ce (CLYC-6), natural Li-glass scintillator (GS10) and liquid scintillator EJ-309) have been characterized for their abilities to attenuate thermal neutrons, fast neutrons and gamma-rays. Recent studies regarding these materials overlook these fundamental characteristics, which can directly affect the design process of advanced imaging systems such as Compton cameras and dual particle imaging systems. The response of each featured material to these three types of radiation fields was simulated with two different Monte Carlo codes, MCNP6 and Geant4. The results indicated that among these four materials, natural Li-glass scintillator (GS10) has the highest thermal neutron detection efficiency and the highest elastic scattering efficiencies. However, the attenuation of fast neutrons was found to be the most severe in EJ-309 liquid scintillator. When gamma-rays are considered, it was found that the mass attenuation coefficient of CLYC and CLYC-6 is the highest of the four materials considered when energies lower than 1 MeV are incident. It is intended that this work will lead to the design and the build of an advanced prototype three stage Compton Camera which will be sensitive to both neutrons and Gamma rays.

show abstract

Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors

Cited by 23 publications

References 17 publications

An investigation into a suitable scintillator for localising neutron capture within a detector

An investigation into a suitable scintillator for localising neutron capture within a detector

Novel neutron detectors based on the time projection method

Material optimization in dual particle detectors by comparing advanced scintillating materials using two Monte Carlo codes

Contact Info

Product

Resources

About