D2O bank

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Relative photon flux

Relative photon flux obtained during the experiment using D2O target.

Flux 4111.png

Flux 4126.png

Flux 4138.png

Flux 4148.png

Flux 4161.png

Flux 4162.png

Flux 4164.png

Flux 4185.png

Flux 4186.png

Flux 4187.png

Normalization?

Flux fluctuation over the runs:

run # equivalent 1 corresponds to run 4187, 2 - 4186, 3 - 4185, 4 - 4164, 5 - 4162, 6 - 4161, 7 - 4148, 8 - 4138, 9 - 4126, 10 - 4111.

Flux fluctns.png

RunTime runNum.png

The thing is that the pair spectrometer is sensitive to the low energy background which may be present in the beam (e- beam finite size and, hence, scraping) so the value of the flux may be affected by low energy component. This thing may not be reflected in the number of neutrons detected by the neutron detectors. So, it is arguable that the pair spectrometer can be used for the flux normalization procedure. One has to investigate the energy spectra of the positrons detected.

Neutron energy spectra

Neutron energy spectra restored from all the runs with D2O target are plotted below. Statistical error bars only presented. All the histograms have same number of channels.

Neutron energy D2O bank1.png


Neutron energy D2O bank2.png

Neutron number vs neutron detector central angle is plotted below:

NeutronNum angleD2O.png

Neutron energy spectra including BKG and photon peak area

DetE neutron energy D2O bank LH.png


Neutron TOF spectrum fit

Cumulative neutron ToF spectrum obtained with Det E and fit with the function that is combination of Gaussian and Landau distribution

y = A*PDF[NormalDistribution[[math]\mu[/math],[math]\sigma[/math]], x]+m*PDF[LandauDistribution[p, a], x], where A=6800, [math]\mu=119 ns[/math], [math]\sigma=8 ns[/math], m=37000, p=135.25, a=12.08.

DetE d2o tof fit2.png

Relative contribution of the photon peak into the neutron region:

Region 1 Region 2
Decomposed fit function Contamination of the the neutron region by photons

Fitting with ROOT:


The tof spectrum obtained with H2O target is presented below:

Region 1 Region 2
Fit of the photon peak Decomposed fit of the photon peak


Region 1 Region 2
Fit of the photon peak Decomposed fit of the photon peak



Region 1 Region 2
Separate ToF spectra superimposed Fit with the H2O photon peak function


Region 1 Region 2
Separate ToF spectra superimposed Fit with the H2O photon peak function


Region 1 Region 2
Fit function Contamination of the the neutron region by photons


Region 1 Region 2
Fit function Fit of the BKG by linear fcn

Detector array setup.png


Lead shielding thickness in front of the detectors/-HV:

DetE - 4" / E1,E2 -> 1650 V, 1750 V

DetM - 4" / M1,M2 -> 1600 V, 1750 V

DetF - 3" / F1,F2 -> 1700 V, 1700 V

DetG - 2" / G1,G2 -> 1700 V, 1650 V

DetH - 2" / H1,H2 -> 1730 V, 1650 V

DetK - 2" / K1,K2 -> 1755 V, 1600 V

DetI - 2" / I1,I2 -> 1650 V, 1700 V

Neutron singles for every PMT:

N singles DU.png


The graphical data on the neutron singles:

File:N singles DU data.pdf


The background was subtracted assuming that it has linear change and the neutron area is above the linear background (see picture above):

Det Eff NObkg4.png


Region 1 Region 2
Fit function Contamination of the the neutron region by photons


TOF spectrum of the neutrons created in the photofission of DU:

Fitting of the raw neutron ToF spectrum:


Region 1 Region 2
Decomposed fit function Contamination of the the neutron region by photons



Region 1 Region 2
Decomposed fit function Contamination of the the neutron region by photons

Detector efficiency

The main experimental setup used to determine the neutron detection efficiencies is shown below:

Detector layout wrt photon2.png

The relative neutron yield obtained by weighting the D2 photodisintegration cross section by bremsstahlung photon flux and solid angle of each of the detector is plotted below as a function of the neutron kinetic energy recalculated from the photon energy using simple kinematics:

Weighted D2 xsection.png

As an example of the efficiency calculation let's find the efficiency of Det M in terms of the known absolute efficiency of Det E (14%):

For the efficiency calculation see slide 15 of [1]

[math]\frac{\epsilon_E}{\epsilon_M} = \frac{N_n^E \cdot Area_M}{N_n^M \cdot Area_E}[/math], [math]\epsilon_M = \epsilon_E \cdot \frac{N_n^M \cdot Area_E}{N_n^E \cdot Area_M}[/math]

Without regards to the neutron energy range one gets the following:

[math]\frac{0.14}{\epsilon_M} =\frac{5932 \cdot 7.92E-5}{2982 \cdot 5.83E-5}[/math] and, hence, [math]\epsilon_M = 5.1 %[/math]

[math]\epsilon_F = 14.8 %[/math]

However, doing the same calculation fro the rest of the detectors one will get

[math]\epsilon_G = 33.3 %[/math]

[math]\epsilon_H = 113.9 %[/math]

[math]\epsilon_K = 126.6 %[/math]

[math]\epsilon_I = 117.05 %[/math]

In order to get the correct values of the neutron detection efficiency for the detectors I, K and H we did another calibration run where the D2O target was moved towards the neutron detectors as shown below:

DetI calibr setup.png

The solid angles changed and were obtained from the simulation:

[math]\delta \Omega_G = 0.0037 sr[/math]

[math]\delta \Omega_H = 0.0067 sr[/math]

[math]\delta \Omega_K = 0.1 sr[/math]

[math]\delta \Omega_I = 0.099 sr[/math]


The relative neutron yield obtained by weighting the D2 photodisintegration cross section by bremsstahlung photon flux and solid angle of each of the detector is plotted below as a function of the neutron kinetic energy recalculated from the photon energy using simple kinematics:

DetI calibr yield2.png

From the experimental data it was defined the total number of neutrons detected by the neutron detectors I, K and H during the calibration run:

DetG calibr adj d2o.png

DetH calibr adj d2o.png

DetK calibr adj d2o.png

DetI calibr adj d2o.png


Nn(I) = 470

Nn(K) = 3159

Nn(H) = 2063

Nn(G) = 437

Now we can calculate the efficiency of the detectors I, K, G and H in terms of the efficiency of detector E obtained during the regular calibration run:

Det effcy table cumulative2.png

23 5vs156 5.png

Data on the relative effcy using Cf-252 and Co-60

N g det relative effcyDD.png


Data on the effcy using neutron single events from U-238 fission

In order to calculate the neutron efficiency the data on the photofission of U-238 were taken from [2]. Also the efficiency of the Det E was measured separately and was found to be 14 %. It was asssumed that the single neutrons from FFs were emitted isotropically. Hence, the difference in the neutron counts for different detectors is introduced by the solid angle and intrinsic efficiency differences. Since the efficiency of the Det E is known (14%) it is possible calculate the neutron counts for the case when the neutron efficiency is 100%: 13877*100%/14% = 99121 neutrons. In the case 100% efficiency for all the detectors the number of neutrons detected is defined by the difference in solid angle. So it is possible to find the expected number of neutrons in the case of 100% efficient detecotrs in therms of the expected number of neutrons in Det E and solid angle difference: for Det M we get the ratio of the solid angles to be 1.118 (see column 4) and hence the number of neutrons detected by 100% efficient Det M is equal to 99121*1.118 = 110845.5 (see column 5). Real value of x% efficiency of the Det M can be found using experimental value of the single neutrons detected and the number of neutrons for 100% efficient Det M as x% = 11,257.0*100%/110845.5 = 10.2% (see column 6). Same algorithm can be applied for the rest of the detectors.

Singles U 238 effcy.png

Energy uncertainty issue

Statistical errors on the number of neutrons per energy bin are not bad, however, big uncertainties in energy come due to the wide width of the photon peak:

Uncertainties neutronEnergy.jpg

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