1. Introduction
In this work, we aim to measure the response of the p-Therphenyl scintillator with a mono-energetic radiation source and determine the light output function. We were motivated by the fact that recently presented studies of light output functions [
1,
2] with the p-Therphenyl scintillator are measured only for neutron energies of up to 8 MeV, which is limiting for practical applications in neutron fields with higher energies, e.g., in particle accelerator laboratories.
Determining the scintillator's light output function accurately is crucial for Monte Carlo simulations of scintillation detector responses. It is well established that protons and electrons of the same energy produce light pulses of different intensities due to differences in ionization density. The light output function captures the nonlinear relationship between proton energy (MeV) and the scintillator's light output, typically expressed in terms of electron equivalent energy (MeVee), reflecting the scintillator's response as if the deposited energy were due to electrons.
The p-Therphenyl scintillator has been placed in a field of mono-energetic radiation over a wide energy range (1.1 to 19 MeV). In this energy range, a new, more accurate light output function has been determined. Furthermore, we carried out a comparison of the PSD capability between the p-Terphenyl scintillator and the well-known NE-213 scintillator. Detection efficiency functions for both scintillators were calculated by the Monte Carlo method.
2. Materials and Methods
2.1. Materials
A solid cylindrical scintillation detector p-Terphenyl of (diameter 45 mm × thickness 45 mm) with PSD properties has been studied in this work. The detector was mounted to a Hamamatsu R6231 photomultiplier tube with an effective diameter of 46 mm, using optical silicon rubber. The optical transmission of the interface was 90%. The photomultiplier was connected to an active voltage divider.
The p-Terphenyl, also known as 1,4-Diphenylbenzene or p-Diphenylbenzene, is a white crystalline solid that is highly soluble in organic solvents such as ethyl acetate, benzene and toluene.
The p-Terphenyl has a molecular formula of C6H5C6H4C6H5 (C18H14) and a molecular weight of 230.31 g/mol. The compound is derived from three phenyl groups connected by a single bond, giving it a linear structure. The p-Terphenyl product number CAS 92-94-4 is meticulously manufactured to ensure a purity level of 99.5%.
2.2. Digital Neutron–Gamma Spectrometer
The digital spectrometer (
Figure 1) is built as a modular system, allowing for the use of different types of scintillation detectors. The preamplifier splits the signal from the detector into two branches. Each branch is differently amplified and digitized by a separate ADC. Different amplification increases the dynamic range of particles that the spectrometer is able to process.
The input analog signal from the p-Terphenyl detector is digitized with a fast 12-bit analog to digital converter with a sampling frequency of 1 GHz. Digital signal processing is implemented into FPGA. FPGA is able to process all data flowing from the ADC (12 Gbits per second). The spectrometer is connected with a computer via an optical ethernet of 10 Gbit.
2.3. Experimental Setup
The first experimental measurements have been performed at the PTB Ion Accelerator Facility, where mono-energetic neutron fields are produced via selected reactions of proton and deuteron beams with light- or medium-weight target nuclei. The measurements were carried out in open geometry in the low-scattering hall, where the contribution of scattered neutrons is minimized by having grid floors [
3,
4].
Two neutron energies, 2.5 and 19 MeV, were used in this experimental campaign. The reactions
3H(p,n)
3He and
3H(d,n)
4He on a titanium tritium target with a density of 1831 μg/cm
2 were used. The mean neutron energy was obtained at a neutron emission angle of zero degrees with respect to the direction of the incident beam. The experimental arrangement is shown in
Figure 2.
The second measurements have been carried out in the laboratory with experimental reactor LVR-15 at Research Center Rez (CVR), Prague. Well defined moderate neutron spectra with energies, see
Table 1, have been measured at the end of the horizontal beam port. Thermal neutrons and gammas was reduced via filter composed of
6Li, Cd, Bi, Pb. The experimental arrangement at CVR is shown in
Figure 3.
A 1 m wide silicon single crystal was used as moderator of the neutron spectra. The moderated spectrum has characteristic neutron energies; see
Figure 4.
2.4. Methods
The digital spectrometer provides both neutron and photon spectra. The measured spectra are calibrated using gamma-ray sources in keVee units. Pulse integrals are discretely divided into measurement bins. The Compton edge method was used for energy calibration [
6]. The position of the Compton edge can best be determined if the properly folded theoretical distribution is fitted to the experimental photon spectrum by a least square fit including only the region of the Compton edge. The linear transformation coefficients were derived from positions of the Compton edges in the spectra of two gamma-ray sources
137Cs and
60Co. Sources of activity 350 kBq have been placed on the center of the front face detector. Measurement time has been determined in accordance with count rates from the detectors. The surrounding background has been subtracted from the measured spectra.
Data were acquired over a time of 2 h for each measurement. Subsequently, these data have been used to calculate light-output parameters and the PSD matrix of the p-Terphenyl scintillator.
The digital spectrometer has incorporated the integration method [
7] for recognition of neutron and photon pulses. The integration method is based on the principle of pulse charge comparison. The PSD parameter is calculated to recognize neutron and photon events:
where T0 corresponds to the beginning of the pulse, T
tail is an optimized beginning of the tail part of the pulse and T
end is an optimized end point of the pulse (see
Figure 5). The optimized PSD parameters for the p-Terphenyl scintillator were set the same for all performed experiments, i.e., T
tail = 16 ns and T
end = 96 ns.
The experimental measurements of the scintillator response spectra were performed using the digital spectrometer in the laboratories CVR and PTB. The neutron response spectra have been identified employing the PSD method.
A summary of the incident neutron energies used in the experiments is given in
Table 1. The edge with the highest equivalent electron energy in the neutron response spectrum corresponds to the maximum energy deposited in the scintillator by the neutron-reflected proton.
3. Results
The pulse-shape discrimination capability of the p-Terphenyl scintillator coupled to the fast digital spectrometer has been evaluated for selected energy of 14 MeV. We carried out the same measurement with the equivalent NE-213 detector. We studied the PSD capability (see Equation (1)) for each measured detector. Two-dimensional graphs have been created (see
Figure 6).
Selected results of neutron/gamma discrimination quality are shown in
Table 2. The critical value of Figure of Merit (FoM) 1.27 is an indicator of good neutron/gamma separation [
8,
9]. The gray fields indicate gamma energies where FoM values exceed the critical value. According to the combination of FoM and energy parameters, we can evaluate quality of neutron/gamma separation.
The detection efficiency calculations of the p-Terphenyl scintillator and an equivalent detector NE-213 has been performed using a Monte-Carlo MCNP 6.2 code [
10]. The equivalent detector NE-213 has the same geometry as the p-Terphenyl scintillator. We use the tally F8 for charge particles. The efficiency curves for the p-Terphenyl and the NE-213 equivalent detector, with the same 100 keVee threshold, are shown in
Figure 7.
For neutron energies of less than 1 MeV, the p-Terphenyl scintillator has a slightly higher efficiency, no more than 4%, compared to the NE-213 detector. On the contrary, at higher neutron energies, the efficiency of the NE-213 detector is higher by up to 6%.
The normalized light-yield spectra for p-Therphenyl scintillator in selected mono-energetic neutron beams are shown in
Figure 8 as well as the edges of the proton spectrum for each measured neutron energy. The proton edges give an overview of the equivalent energies that were used to calculate the light output parameters. An overview of the equivalent energies of the proton edges is given in
Table 3.
The light output function is important for unfolding the neutron spectra from the pulse height distribution. The light output function is described by the following formula [
11]:
where
Ee is the electron energy in MeVee and
L0,
L1 are fitting parameters. The experimental data have been processed in the Matlab SW and the fit function was employed. Calculated fit parameters and their confidence bound of 95% are stated in
Table 4.
The light output function is shown in
Figure 9 with 95% confidence bounds. There is a good agreement between the measured data and fitted function (R-Square = 0.9998 and Adjusted R-Square = 0.9998).
4. Discussion
The light output function and pulse-shape discrimination capability of the p-Therphenyl scintillator have been measured and evaluated over a much wider energy range than previously reported.
Light output parameters (see
Table 4 of the p-Therphenyl scintillator) have been determined from the data fitted by the function described in Equation (2). Previous studies concerned with the same issue have reported the results of light output functions in their publications (see ref. [
1,
2]). The time of flights method was used in the publications [
1,
2]. In the case of results [
2], the light output function was determined in the energy range of 0.8 to 4 MeV using the
252Cf source. In the study [
2], the light output function was determined in the energy range of 0.2 to 8 MeV.
We compared our results with previously presented results of light output functions (see
Figure 10). Our light output function was determined in the wide energy range (1.1–19) MeV. The results reported in study [
1] are higher in comparison with our values, and, conversely, our values are higher than the results stated in study [
2] for energies less than 8 MeV. The main contribution of our work is the overall refinement of the light output function for the p-Therphenyl scintillator.
The ability of the p-terphenyl scintillator to recognize the pulse shape was compared with the equivalent neutron detector NE-213. As can be seen in
Figure 6 and
Table 2, the neutron–gamma separation is not nearly as sharp and sufficiently separated (separation parameter) as in the case of the NE-213 detector. The p-Therphenyl scintillator has worse properties in this respect than the NE-213 detector, which is to be expected. Some liquid scintillators are considered, although health and fire hazards make them unsuitable for certain applications. Solid-state scintillators like p-Therphenyl are usable for fast neutron detection in dosimetry and homeland security applications.
The results will be used in the future, especially in the design of new detectors and in simulations of radiation transport using a Monte Carlo code. Using the new light output function parameters (see
Table 4) will ensure more accurate calculations and thus achieve more realistic results in practical applications.
Author Contributions
Conceptualization, A.J., Z.M. and M.K.; methodology, A.J. and Z.K.; software, Z.M.; validation, J.Č.; data curation, A.J., Z.K. and M.K.; formal analysis, A.J. and Z.K.; writing—original draft preparation, A.J.; supervision, Z.K. and Z.M.; project administration, A.J., Z.M. and M.K.; funding acquisition, A.J., Z.M. and M.K. All authors have read and agreed to the published version of the manuscript.
Funding
This research was funded by the Ministry of Education, Youth and Sports of the Czech Republic, project No. LM2018118 “VR-1—Support for reactor operation for research activities” and by use of the infrastructure Reactors LVR-15 and LR-0 project LM 2023041.
Data Availability Statement
Data will be made available upon request.
Acknowledgments
We are very grateful to the Physikalisch-Technische Bundesanstalt at Braunschweig for allowing the measurements in the laboratory with the Ion Accelerator.
Conflicts of Interest
Author Aleš Jančář, Zdeněk Kopecký and Jiří Čulen are employed by the company VF NUCLEAR. Michal Košťál is employed by the company Research Centre Řež Ltd. The remaining authors declare that the research was conducted in the absence of any commercial or financial relationships that could be construed as a potential conflict of interest.
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