D2O bank

Relative photon flux

Relative photon flux obtained during the experiment using D2O target.

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.

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 number vs neutron detector central angle is plotted below:

Neutron energy spectra including BKG and photon peak area

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=36158.6, p=136.25, a=12.07.

Decomposed fit function:

Relative contribution of the photon peak into the neutron region:

Experiment	Simulation
Simulation w/ y-resolution; Solid angle = 0.093 sr	Simulation w/o y-resolution; Solid angle = 0.092 sr

Detector efficiency

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

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:

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:

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:

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:

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:

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

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.

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: