scholarly journals CHARACTERIZATION AND COMPARSION OF NEUTRON GENERATORS OF IEC AND LINEAR D-T BY THE SPECTROMETRIC SYSTEM NGA-01

2021 ◽  
Vol 247 ◽  
pp. 18004
Author(s):  
Zdenek Matej ◽  
Michal Kostal ◽  
Evzen Novak ◽  
Petr Alexa ◽  
Radim Uhlar ◽  
...  

This article focuses on description of two different neutron fields from linear and cylindrical Inertial Electrostatic Confinement (IEC) neutron generators. Both of these generators are well defined and commonly used. They use a deuterium-tritium reaction that produces neutrons with energies in the range 13 – 16 MeV, depending on the direction and the energy of the incoming deuterium nucleus. Two-parametric spectrometric system for neutron/gamma mixed fields NGA-01 was used to characterize neutron spectra in the proximity of generators. The cylindrical 45x45 mm stilbene scintillator was connected to this device using an active voltage divider. This way, we were able to measure neutron energies in the range 1 - 15 MeV while filtering out gamma radiation, even when counts per second is high. For the neutron spectrum calculation recoil spectra using deconvolution through maximum likelihood estimation was used. Measured neutron spectra have been compared with simulations realized via MCNP6. According to the theoretical prediction, these two types of generators produce different neutron fields. In case of the linear generator the target is very close to point located tritium bombarded by deuterons. Thus the neutron spectrum varies depending on the angle between the detector axis and the axis of the generator. Both experimental results and simulation show a shift of the neutron energy peak in pulse height histogram. For IEC type generators the neutron spectrum is more complicated. The shape and the position of the neutron energy peak depend heavily on the position of the detector. The most prominent effect is in the position in the plane perpendicular to the generator axis. In this case, the peak splits into two peaks that can be measured and distinguished. These results were verified by the diamond detector which was also used for characterization of the IEC type generator.

1955 ◽  
Vol 33 (5) ◽  
pp. 219-224 ◽  
Author(s):  
D. B. James ◽  
W. Kubelka ◽  
S. A. Heiberg ◽  
J. B. Warren

Two boron trifluoride proportional counters, one containing normal isotopic boron and the other containing boron enriched to 96% B10, have been irradiated with 4.87-Mev. neutrons from the reaction D(d, n)He3. In addition to the reactions B10(n, α)Li7 and B10(n, α)Li7* with Q-values of 2.79 Mev. and 2.31 Mev. respectively, two other reactions have been observed. These are (i) F19(n, α)N16* with a Q-value of −1.77 ± 0.15 Mev. and (ii) either B10(n, p)Be10 or, much more probably, B10(n, t)Be8 with a Q-value of 0.35 ± 0.20 Mev. Owing to the presence of these two reactions, the analysis of complex fast-neutron spectra by the use of such counters is not feasible.


2020 ◽  
Vol 239 ◽  
pp. 18005
Author(s):  
Bohumil Jansky ◽  
Jiri Rejchrt ◽  
Evzen Novak ◽  
Anatoly Blokhin

The leakage neutron spectra measurements have been done on benchmark spherical assemblies with Cf-252 source in center of 1) heavy water sphere with diameter of 30 cm (with Cd cover) and of 2) iron spheres with diameter of 100 cm and 50 cm. It has been stated for years that transport calculations by iron overestimate measured spectra in energy region around 300 keV by about 20-40 % (calculation to measurement ratio C/E = 1.2-1.4). The influence of an artificial changes in cross-section XS-Fe-56 (n,elastic)designed by IAEA, Nuclear Data Section, has been studied on the iron spheres. Influence of those XS-corrections to calculated neutron spectrum is presented.


1962 ◽  
Vol 40 (1) ◽  
pp. 33-48 ◽  
Author(s):  
K. W. Geiger ◽  
C. J. D. Jarvis

The neutron energy spectra from Po–B10(α,n) and Po–B11(α,n) sources have been determined by the nuclear emulsion method and with a proton recoil spectrometer. Gamma spectra have also been measured. The Po–B10 neutron spectrum extends to an energy of 6.0 Mev and shows two peaks, at 1.0 and 3.0 Mev. The lines in the gamma spectrum are not in coincidence with neutrons but are caused by competing reactions. The Po–B11 neutron spectrum shows one peak at 2.7 Mev; the maximum energy observed is 5.0 Mev. One γ-ray line at 2.32 Mev with an intensity of 5% of the neutron emission rate is detected in the gamma–neutron coincidence measurements. The experimental neutron energy spectra have been compared with calculated spectra and are compatible with the gamma measurements, as well as with published level schemes for the residual N13 and N14 nuclei. In the case of the Po–B10 source only one-third of the neutrons are produced by the B10(α,n)N13 reaction and the remainder has to be accounted for by the B10(α,np)C12 reaction.


1968 ◽  
Vol 46 (13) ◽  
pp. 1527-1536 ◽  
Author(s):  
L. Van der Zwan

The neutron spectra from 9Be(α, n) sources are calculated for the α emitters 241Am, 210Po,and 239Pu. For a Pu–Be source, peaks are found at neutron energies of 0.75, 1.20, 2.10, 3.15, 4.95, 6.50, 7.75, and 9.65 MeV. Similar peak positions are found for sources made with 241Am and 210Po. The effect of the α-energy losses in the α-emitting material is studied by means of a simple model consisting of clusters of the α-emitting material embedded in a matrix of beryllium. For sources composed of clusters of AmBe13 or PuBe13 in beryllium, the changes in shape of the neutron spectrum are minor as the cluster size is increased from 0.5 to 20 μ. However, for sources consisting of clusters of Pu and Am or Po embedded in beryllium, the spectrum is considerably distorted as the cluster size is varied from 0.5 to 10 μ. The neutron yield per 106 α particles is calculated for sources having Am, Po, or Pu clusters ranging in size from 0 to 20 μ and AmBe13 or PuBe13 clusters ranging from 0 to 40 μ. The percentage of neutrons below 1.5 MeV including the contribution from the multiparticle reaction 9Be(α, αn)8 Be is estimated to be 16% for an AmBe13 type of source and 12% for a PuBe13 type of source, each with a cluster size of 0.5 μ.


1964 ◽  
Vol 42 (6) ◽  
pp. 1030-1036 ◽  
Author(s):  
D. C. Santry ◽  
J. P. Butler

Excitation curves for the reactions Fe56(n, p)Mn56 and Co59(n, α)Mn56 have been measured by the activation method from near threshold energies to 20.3 Mev. The measurements are relative to the known cross section for the S32(n, p)P32 reaction. Cross sections for both reactions increase smoothly with neutron energy and reach maximum values of 119 ± 4 mb for the Fe56(n, p) reaction at 13.6 Mev and 30.0 ± 0.9 mb for the Co59(n, α) reaction at 14.5 Mev. Above 15 Mev both cross sections decrease with neutron energy. From the excitation curves effective cross-section values for a fission-neutron spectrum have been calculated as 1.04 ± 0.05 mb for the (n, p) reaction and 0.140 ± 0.007 mb for the (n, α) reaction.


2020 ◽  
Vol 13 ◽  
pp. 222
Author(s):  
M. Manolopoulou ◽  
M. Fragopoulou ◽  
S. Stoulos ◽  
C. Koukorava ◽  
M. Zamani

Two helium filled proportional counters (He-3, He-4) were irradiated with neu- trons in the energy range 0.025 eV - 10.7 MeV, in the Tandem accelerator, NCSR Demokritos, Athens. The full energy peak in He-3 proportional counter as well as the recoil peaks in He-3 and He-4 counters show linear dependence with neutron energy. A study of gamma ray contribution to the neutron spectra of He-4 counter was performed as a function of the pulse shaping time.


2014 ◽  
Vol 29 (1) ◽  
pp. 1-9
Author(s):  
Senada Avdic ◽  
Predrag Marinkovic ◽  
Alma Osmanovic ◽  
Izet Gazdic ◽  
Sejla Hadzic ◽  
...  

This paper deals with the design of a novel spectrometer of fast neutrons in nuclear safeguards applications based on the liquid organic scintillator EJ-309 with materials of different thickness surrounding the detector. The investigation was performed on the simulated data obtained by the MCNPX-PoliMi numerical code based on the Monte Carlo method. Among the various materials (polyethylene, iron, aluminum, and graphite) investigated as layers around the scintillator, polyethylene and iron have shown the most promising characteristics for evaluation of fast neutron energy spectra. The simulated pulse height distributions were summed up for each energy bin in the neutron energy range between 1 MeV and 15 MeV in order to obtain better counting statistics. The unfolded results for monoenergetic neutron sources obtained by a first order of Tikhonov regularization and non-linear neural network show very good agreement with the reference data while the evaluated spectra of neutron sources continuous in energy follow the trend of the reference spectra. The possible advantages of a novel spectrometer include a less number of input data for processing and a less sensitivity to the noise compared to the scintillation detector without surrounding materials.


2016 ◽  
Vol 19 (4) ◽  
pp. 131-136
Author(s):  
Thu Thi Ai Nguyen

For the design of ADS (Accelerator Driven System), it is important to study neutron spectra and details of nuclear reactions induced by neutrons. Furthermore, neutron energy and angular distribution data are important for a correct simulation of the propagation of particles inside a spallation target and the geometrical distribution of the outgoing neutron flux. Many experimental results are available for thin targets and massive targets additional studies of neutron spectra and neutron production were investigated to design target for ADS with incident proton energies up to 3 GeV. In our study, the angular distribution and the neutron energy spectra are reported for the (p,n) reaction on target nuclei such as Pb, U, W with energy from 50 MeV to 350 MeV calculated with database of JENDL-HE 2007. We obtain a set of data about the angular distribution and energy spectra of produced neutrons on some heavy targets with energy ranges as stated above. From the results of neutron spectra, the paper also gives many comments to recommend a choice of materials for target and energies for accelerating proton beam . From the angle distribution of neutrons generated in (p, n) reactions on the different targets with the different energies of proton, the solutions to arrange the reflection bars in reactor proposed. A comparison is also made to improve the reliability for calculation of the paper.


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