Digital analysis of scintillator pulses generated by high-energy neutrons. Jan Novák, Mitja Majerle, Pavel Bém, Z. Matěj 1, František Cvachovec 2, 1 Faculty of Informatics, Masaryk University in Brno, Czech Republic 2 University of Defence, Brno, Czech Republic

High energy neutron detection High energy neutron detection is generally based on the nuclear interaction basis. Charged particles produced in the n reaction on the nuclei are detected by usual charged particle detection methods. For this purpose, well known (n,p) elastic scattering is frequently used.

3 Proton Recoil Telescope for Neutron Spectroscopy ■ The Proton Recoil Telescope (PRT) is based on the detection of protons in the n+p scattering on a thin hydrogenated target. ■ By correcting for the energy dependent efficiency, the energy spectrum for the neutrons emitted by the source is determined from the detected proton spectrum, on the kinematics relations basis. ■ Protons are detected at defined angle by telescope of Si detectors. Φ 7,0 mm 209,0 mm 456,5 mm 7 Li 12 C CH 2 Φ 14,0 mm m mg Tube, SS, T 2 mm CH 2 (B) Fe 30x30x60 mm 3 Beam spot on Li target Φ(FWHM) 4 mm mm 44,4o44,4o The PRT is proposed to detect neutron spectrum at short distances from the source where TOF method is not applicable Si-D

4 Simplified reconstruction of neutron spectrum ■ Response functions were superposed by optimization procedure to fit measured proton-recoil spectrum. Multiplication factors pertaining to response functions create resulting n spectrum. ■ A code for the reconstruction of neutron spectrum from mesured proton recoil spectrum was developed. In the code, the response function is based on the n+p differential cross section knowledge (LA-150h library) and the n+p scattering kinematics. ■ The model of response functions was calculated including the realistic geometry arrangement of the neutron source-radiator-detector set. As a simplified approach to the reconstruction procedure, the effects of secondary scattered neutrons were neglected.

NE 213 scintillator In the NE 213 scintillator, protons are scattered by neutrons. Moreover, at higher neutron energy (over 8 MeV), number of another processes producing charged particles contributes to overall scintillator response. Protons and another charged particles excite atomic levels, whose number is proportional to energy loss of the particle. Therefore, ray caused by the deexcitation has an intensity proportional to energy lost in the scintillator. The light ray is converted to an electric pulse and amplified by the photomultiplier base assembly Ortec 265. Light gain dependency on the proton energy is empirically determined: L p (E p )= E 2 0< E < 1.5 MeV L p (E p )= E E E < E <3.5 MeV L p (E p )= E E E 3 3.5< E < 8.0 MeV L p (E p )= E8.0 < E < 20 MeV The response function shape is determined mainly by the (n,p) angular distribution and by the scintillator geometry.

Neutron-gamma discrimination In the real experiment, gamma photons interact with the scintillator also. It is necessary distinguish neutron and gamma events. Gamma photons scatter electrons, therefore the atomic levels are excited by a different way. n-gamma discrimination using pulse shape analysis is feasible. We have two possibilities of the neutron- gamma discrimination: 1.Pulse rise time analysis. Pulses originated from neutrons and gammas are distinguished on the rise time duration. 2.Pulse shape analysis based on the comparison of the overall pulse area and the pulse part area beginning from a fixed sample. The ratio of two areas: Rise time

1. Pulse rise time analysis In the past, we performed two-parametrical data processing. Besides the pulse amplitude data collection, the pulse was processed by a second way. The PSA generates start and stop pulses, which are derived from 10% and 90% of the pulse amplitude. The TAC converts the time delay between start and stop pulse to amplitude. Hence, amplified NE 213 pulse amplitude and the amplitude containing the pulse rise time are together saved in the time coincidence. In the optimal conditions, we distinguished neutron pulses for neutron energies from 0.5 MeV. Ne 213 Converter PSATAC Start Stop HV PC

2. Pulse shape analysis based on the areas comparison Present level of the digital signal processing enables us to process very short pulses by the digital oscilloscope technique. Our oscilloscopic card has 10 bits AD converter with maximal sampling frequency 500 MHz. The pulse information is given by some tenths of samples, because the maximal pulse duration is 100 ns. At the present time, all samples are recorded to the PC hard disk. Therefore, we are able to collect pulse samples with relatively low dead time at pulse frequency up to 1000 pulses/s. But now we try preprocess pulse samples before their transfer by PCI bus and saving on the hard disk. This way will lead to saving of the markedly lower parameter number. Advantage of this way will be achievement of the markedly higher pulse frequency. Moreover, the PC hard disc volume requirements will be decreased. Ne 213 HV PC with card

Neutron-gamma discrimination results On the figure, the neutron and gamma pulses of the 252 Cf neutron source are separated very well. Our NE 213 set-up was used, pulses were digitized by digitizer of Faculty of Informatics, Masaryk University in Brno. In our experimental set-up, the PuBe neutron source was used. The neutron and gamma pulses are clear separated. The A 1 area is integrated from 8 th channel after pulse maximum, what is 16 ns after maximum. However, this method is extremely sensitive to signal-noise distance mainly due the A 1 area integration.

Conclusions and visions Advantages of the pulse sampling: High event frequency (in the mode of the pulse processing before saving). Possibility of the on-line data analysis for the experimental set-up correction. Possibility of the processing algorithm development on the saved samples. Absolute freedom in the processing algorithm choice. Portability. Challenges: To solve the problem with the high neutron-gamma sensitivity to signal-noise distance. To implement the on-line pulse processing before the data PCI transfer and saving on the hard disc. To choose and to handle the optimal method for the neutron pulse spectra deconvolution in order to neutron spectra obtaining.