Neutron Conversion Foil, Neutron Detecting Device with Such a Foil, and Method for Operating Such a Neutron-Detecting Device

Abstract

A neutron conversion foil for being used in a neutron detector includes a substrate having a first and second side. The substrate is covered at least on one of the first and second sides with a neutron conversion layer made of a neutron reactive material and being capable of capturing neutrons to thereafter emit light and/or charged particles. The neutron conversion foil is transparent to light such that light originating from the conversion of neutrons can pass through one or several of the neutron conversion foils and thereafter be collected and detected by a light sensing device.

Claims

1. A neutron conversion foil for being used in a neutron detector, said neutron conversion foil comprising a substrate having a first side and a second side, whereby said substrate is covered at least on one of said first side and said second side with a neutron conversion layer made of a neutron reactive material and being capable of capturing neutrons to thereafter emit light and/or charged particles, and whereby said neutron conversion foil, is transparent to light such that light originating from the conversion of neutrons can pass through one or several of said neutron conversion foils and thereafter be collected and detected by a light sensing device.

2. The neutron conversion foil as claimed in claim 1, wherein said substrate covered on said first side and said second side with a neutron conversion layer made of a neutron reactive material and being capable of capturing neutrons to thereafter emit light and/or charged particles.

3. The neutron conversion foil as claimed in claim 1, wherein said neutron conversion layer contains Li-6 or B-10.

4. The neutron conversion foil as claimed in claim 3, wherein said neutron conversion layer contains LiF and a suitable binder in a weight ratio between 1:1 and 15:1, and that appropriate measures such as LiF nanosizing or refractive index matching are performed to ensure high transparency.

5. The neutron conversion foil as claimed in claim 3, wherein said neutron conversion layer has a layer thickness of between 1 m and 40 m, especially between 3 m and 20 m.

6. The neutron conversion foil as claimed in claim 1, wherein said substrate is a transparent PET foil.

7. The neutron conversion foil as claimed in claim 6, wherein said transparent PET foil has a thickness of between 2 m and 19 m.

8. The neutron conversion foil as claimed in claim 1, wherein each of said neutron conversion layers is overcoated with a wavelength shifting layer being capable of shifting short wavelength light impinging upon it and reemitting light with a wavelength to which said neutron conversion foil is transparent.

9. The neutron conversion foil as claimed in claim 8, wherein said wavelength shifting layer contains Tetra Phenyl Butadiene (TPB), an organic wavelength shifter, or an organo silicate compound.

10. The neutron conversion foil as claimed in claim 9, wherein said wavelength-shifting layer has a layer thickness of between 0.05 m and 1 m, especially between 0.05 m and 0.2 m.

11. The neutron conversion foil as claimed in claim 1, wherein that said substrate is a mesh.

12. A neutron detecting device comprising a scintillation volume filled with a scintillating material such as a noble gas, wherein one or more neutron conversion foils according to claim 1 are provided in said neutron detecting device to be in optical contact with said scintillating material such that charged conversion products arising from said neutron capture in said one or more neutron conversion foils escape into said scintillation volume and produce light, to which said one or more neutron conversion foils is transparent.

13. The neutron detecting device as claimed in claim 12, wherein, at least one light-sensing device is provided in optical contact with said scintillation volume.

14. The neutron detecting device as claimed in claim 13, wherein said at least one light sensing device is a solid state light sensor, especially one of a silicon photomultiplier (SiPM) or pixelated Geiger mode avalanche photodiode.

15. The neutron detecting device as claimed in claim 13, wherein said scintillation volume is composed primarily of a noble gas such as helium, argon or xenon or a mixture of noble gases, such as helium doped with xenon.

16. The neutron detecting device as claimed in claim 15, wherein said scintillation volume is predominantly filled with helium, thereby allowing the simultaneous measurement and distinction of fast neutrons, thermal neutrons, and/or photons and electrons produced by the interaction of photons with a detector wall.

17. The neutron detecting device as claimed in claim 15, wherein said scintillation volume is predominantly filled with xenon, thereby allowing gamma spectrometry to be performed while also measuring neutrons.

18. The neutron detecting device as claimed in claim 13, wherein said scintillation volume contains predominantly PVT or a liquid scintillator, thereby allowing the simultaneous measurement of gammas and neutrons.

19. The neutron detecting device as claimed in claim 14, wherein said at least one solid state light sensor is arranged within said scintillation volume.

20. The neutron detecting device as claimed in claim 15, wherein an in-situ gas purification device such as a getter is immersed in the gas of said scintillation volume, thereby assuring a stable gas composition.

21. The neutron detecting device as claimed in claim 13, wherein said scintillation volume is surrounded by a highly reflective material in the area of which a plurality of light sensing devices can be interspersed.

22. The neutron detecting device as claimed in claim 12, wherein plural neutron conversion foils are arranged in parallel in said scintillation volume.

23. The neutron detecting device as claimed in claim 12, wherein said neutron detecting device is part of a detector system, and wherein a plurality of detector subunits are connected with a control center for evaluating detector data via a wireless network.

24. The neutron detecting device as claimed in claim 23, wherein said neutron detecting device part of at least one of said detector subunits.

25. The neutron detecting device as claimed in claim 24, wherein said neutron detecting device is connected within said detector subunit to a single board computer, which itself is connected to a network unit and comprises detector software and a data aggregation software/network protocol

26. The neutron detecting device as claimed in claim 25, wherein a GPS unit for determining the actual position of said detector subunit is connected to said single board computer.

27. A method for operating the neutron detecting device according to claim 12, wherein signals arising from a neutron conversion in said one or more neutron conversion foils are discerned from signals arising from said scintillation volume by pulse shape discrimination, whereby the signals involving light emitted by said one or more neutron conversion foils typically have a different time structure than the signals from said scintillation volume.

28. The method as claimed in claim 27, wherein light signals arising directly or indirectly from said neutron conversion in said one or more neutron conversion foils are discerned from signals from said scintillation volume alone by pulse shape discrimination, whereby the signals from neutron conversion have a different time structure than the signals from said scintillation volume.

29. A method for operating the neutron detecting device according to claim 12, wherein the presence, the intensity and/or the type of gamma radiation interacting with the scintillating volume is determined by analyzing the distribution of the energy spectrum of the interaction events accumulated during a predetermined period of time of operation, especially in a range from 1 to 100 seconds.

30. A method for operating the neutron detecting device according to claim 12, wherein two overlapping spectral distributions resulting from the simultaneous interaction of gamma radiation and neutron radiation with the scintillating volume and/or the converter foil and being accumulated during a predetermined period of time of operation, especially in a range from 1 to 100 seconds, are analyzed employing statistical methods, whereby a net neutron count rate can be determined by subtracting the spectral response obtained by the gamma radiation from the total spectrum.

Description

BRIEF DESCRIPTION OF THE DRAWINGS

[0044] The present invention is now to be explained more closely by means of different embodiments and with reference to the attached drawings.

[0045] FIG. 1 shows in a longitudinal cross section the structure and function of a single-sided neutron converter foil with a sheet substrate and wavelength shifting properties according to an embodiment of the invention;

[0046] FIG. 2 shows, similar to FIG. 1, in a longitudinal cross section the structure and function of a double-sided neutron converter foil with a sheet substrate and wavelength shifting properties according to another embodiment of the invention;

[0047] FIG. 3 shows in a longitudinal cross section the structure and function of a double-sided neutron converter foil with a mesh substrate and wavelength shifting properties according to another embodiment of the invention;

[0048] FIG. 4 shows, similar to FIG. 2, in a longitudinal cross section the function of a neutron converter foil converting thermal neutrons to conversion products, conversion products escaping the converter foil to enter a scintillation volume, causing the emission of light;

[0049] FIG. 5 shows part of a neutron detecting device or arrangement comprising a stack of several neutron converter foils or membranes similar to FIG. 2, where the light arising from a neutron capture event can pass through said neutron converter membranes and be collected upon light sensing devices, with the help of reflectors.

[0050] FIG. 6 shows an embodiment of a neutron-detecting device, where the neutron converter membranes are thin enough to allow decay products to escape on both sides of the foil, thereby almost doubling efficiency;

[0051] FIG. 7 shows a basic multi-detector scheme comprising several neutron-detecting devices (detectors) according to the invention;

[0052] FIG. 8 shows a special configuration of a multi-detector scheme comprising several neutron-detecting devices (detectors) according to the invention, where the number of channels of the signal processing electronics is reduced to save costs;

[0053] FIG. 9 shows in a partially transparent illustration a preferred embodiment of a neutron detection device according to the invention with a possible meandering suspension of the neutron converter membranes;

[0054] FIG. 10 shows in exploded view details of the device according to FIG. 9;

[0055] FIG. 11 shows details of the head of the device according to FIGS. 9 and 10;

[0056] FIG. 12 shows one of the moderating plates supporting the meandering converter membrane, of the device according to FIGS. 9 and 10 in a top view (a) and sectional view (b);

[0057] FIG. 13 shows a first step in a method for assembling a detector according to FIGS. 9 and 10;

[0058] FIG. 14 shows a second step in a method for assembling a detector according to FIGS. 9 and 10;

[0059] FIG. 15 shows, in a top view, a diagonal two-detector arrangement with detectors according to FIGS. 9 and 10;

[0060] FIG. 16 shows linear multi-detector arrangement with detectors according to FIGS. 9 and 10;

[0061] FIG. 17 shows an embodiment of a neutron-detecting device, where the neutron converter membranes are suspended by welding or gluing several foils to form an accordion style two or three dimensional structure;

[0062] FIG. 18 shows an example of a monitoring detector system with a plurality of neutron detectors in detector subunits positioned at different places and connected via a wireless network with a control center;

[0063] FIG. 19 shows a simplified scheme of a single detector subunit;

[0064] FIG. 20 shows exemplary overlapping energy spectra of Gamma and neutron interaction events accumulated over a certain period of time and the accompanying noise; and

[0065] FIG. 21 shows an analyzing scheme for a spectral distribution according to FIG. 20.

DETAILED DESCRIPTION OF DIFFERENT EMBODIMENTS OF THE INVENTION

[0066] A key element of the present invention is an optically transparent neutron converter foil.

[0067] Transparent in this case means that the foil absorbs only a few % (preferably not more than 1%) of the visible light (especially with a wavelength around 420 nm +/30 nm).

[0068] FIG. 1 shows in a longitudinal cross section the structure and function of a single-sided neutron converter foil according to an embodiment of the invention. The neutron converter foil 10 comprises an optically transparent substrate 11, which is on one side (upper side in FIG. 1) covered or coated with an optically transparent neutron converter layer 12 and an optically transparent wavelength shifting layer 13.

[0069] Substrate 11 is in this case a transparent PET foil with a thickness of between 2 m and 19 m.

[0070] Neutron converter layer 12 contains Li-6 or B-10. Preferably, it contains 95% or higher enriched .sup.6LiF and a suitable binder in a weight ratio between 1:1 and 15:1. It has a layer thickness of between 1 m and 40 m, preferably between 3 m and 20 m. The coating of substrate 11 with neutron converter layer 12 is performed in such a way that the coating is highly transparent and adheres well to substrate 11. Furthermore, appropriate measures such as nanosizing LiF crystals or refractive index matching are performed to ensure high transparency.

[0071] Thin wavelength shifting layer 13 is capable of shifting short wavelength light 15 impinging upon it and reemitting (visible) light 16 with a wavelength to which neutron conversion foil 10 is highly transparent (light 16 in FIG. 1). Wavelength shifting layer 13 contains Tetra Phenyl Butadiene (TPB), an organic wavelength shifter, or an organo silicate compound, and has a layer thickness of between 0.05 pm and 1 pm, especially between 0.05 m and 0.2 m.

[0072] As said before, if short wavelength light 15, such as light emanating from a neighboring noble gas scintillation incident 14, falls upon wavelength shifting layer 13, it gets shifted to visible light 15. The converter membrane is highly transparent to visible light, so that light 16 may cross the foil without notable absorption.

[0073] Neutron converter foil 10 of FIG. 1 is a single-sided foil, i.e. substrate 11 is coated with layers 12 and 13 only on one side.

[0074] However, when the foil is arranged in a scintillation volume, thereby surrounded by a noble gas or other scintillation means, it is favorable to have a double-sided neutron converter foil 10 as shown in FIG. 2. In this embodiment, both sides of substrate 11 are coated with neutron conversion layers 12, 12 and wavelength shifting layers 13, 13. Again, neutron converter foil 10 is highly transparent to visible light 16, which for example has been shifted by one of the wavelength shifting layers 13 and 13. Thicknesses and layer materials of the various layers are the same as for neutron converter foil 10 of FIG. 1.

[0075] According to another preferred embodiment shown in FIG. 3, the substrate 11 is a mesh of polystyrene, polyamide, or other suitable material. Neutron converter foil 10 in this case has the advantage that more neutron conversion material in mesh-embedding neutron conversion layer 12 is ready to convert a neutron into respective decay products, thereby achieving higher efficiency with thinner coatings while minimizing the energy loss of decay products in the substrate.

[0076] An important functionality of the converter membranes or foils 10, 10 and 10 is shown for neutron converter foil 10 in FIG. 4: Incoming neutrons 18 get captured by the neutron converting material, decaying into decay products 17 that can escape into the neighboring scintillation volume causing a scintillation incident 14. Short wavelength scintillation light 15 gets shifted to visible light 16, to which the membrane or foil 10 is transparent.

[0077] FIG. 5 shows an embodiment of the neutron detecting device (detector) 20, where several such double-sided membranes or foils 10 are suspended in a scintillation volume 19, which is for example filled with a noble gas. The surrounding walls are covered with a highly reflective material A such as a dielectric mirror or diffuse reflector with one or more apertures (not shown in FIG. 5), through which photons can impinge on one or more light sensitive devices (B in FIG. 6), such as Silicon Photomultipliers (SiPMs) (41 in FIG. 8). Visible light 16, 16 emanating from the various wavelength shifting layers crosses the foils 10 nearly without attenuation, is reflected reflecting walls (A) and can be collected by light sensitive devices.

[0078] FIG. 6 shows another embodiment of the invention, where in neutron detecting device 20 converter membranes 24 are placed in a scintillation volume 23 between opposite reflectors 21 and 22. For each converter membrane 24, a transparent LiF coating is applied to 1 5 both sides of a substrate 25 made of quartz, polyvinyltoluene or other transparent material. However, care must be taken to keep the transparent layers sufficiently thin, such that gamma radiation does not deposit large amounts of energy by scintillation. Again, decay products (triton 28) of a captured neutron cause a scintillation incident 27, the light of which reaches light sensitive device 29 after crossing the foils 24 several times.

[0079] FIG. 7 shows a possible low cost signal-processing scheme 30 for an array of several detectors 31 according to this invention. The signal-processing unit is composed of a fast multi-channel analogue front-end with 32 channel ASICs units 32 that amplify the signals generated by the SIPMs with detectors 31 and apply a threshold. In a second step, the discriminated signal is fed into a field programmable gate array (FPGA) 33 that measures the pulse width of the signal. Particle to particle and particle to noise discrimination is achieved by applying time coincidence as well as pulse width requirements by means of the FPGA 33. The various sub-units are supplied with power by power supply 34. A microcontroller 35 is used to read-out the FPGA 33, regulate the power voltage on the power supply 34 and manage the device communication with external interfaces.

[0080] FIG. 8 shows an embodiment of the invention, where in a cascading scheme 36 the number of channels 38, 39 of the signal processing electronics (coincidence unit 37) is kept low by cascading several SiPMs 41 of unit cells 40 for cost reasons.

[0081] FIGS. 9 to 14 show a preferred embodiment of a neutron detecting device or detector 42 according to the invention, where a double-sided neutron converter membrane 47 of the kind shown in FIGS. 2 to 4 has a total area of about 5 m.sup.2, arranged in a meandering or accordion style manner in a longitudinal tube 43 (preferably of steel), which is closed by a closure head 44 and contains a scintillation volume 43a filled with noble gas, or the like, through a valve 45 or pinch-off provided on said closure head 44.

[0082] Neutron converter membrane 47 is kept in place by a series of parallel moderating plates 46 oriented perpendicular to the longitudinal tube axis, and being assembled from two separate plate elements 46a and 46b with intertwining fingers (see FIG. 12) that subdivide the gas scintillator volume. The scintillating noble gas is slightly pressurized and contained by tube 43, which may have a diameter of 10 cm. The inside of tube 43 is lined with a highly efficient reflector. Printed circuit boards 50 (FIG. 11) with surface mounted SiPMs run down the center of the detector tube 43 and are connected with outside by means of a connecting cable 48.

[0083] FIGS. 13 and 14 show a possible assembly method of detector 42 according to FIGS. 9 and 10. A foil reel of a (double-sided) converter membrane or foil 47 is used to supply one foil of a width comparable to the length of tube 43. The stack of moderating plates 46 is kept in place, whereby the upper plate elements 46a or 46b have been removed to get access to the open finger structure of the remaining plate elements 46b or 46a. Then, a sufficient length of foil 47 is unrolled from reel 51 and pushed into the slots 53 of the finger structure by means of a parallel arrangement of guide or pushing rods 52.

[0084] When the foil 47 has reached its final position (FIG. 14) thereby showing the meandering membrane pattern 49 of FIG. 12a, the guide rods 52 are removed and all moderating plates 46 are assembled again so that the meandering foil 47 is held in and supported by the plates 46.

[0085] The detector 42 of FIGS. 9 and 10 can be used in different arrangements. FIG. 15 shows, in a top view, a diagonal two-detector arrangement 54 with detectors 42 according to FIGS. 9 and 10 in a container 55 with square cross section.

[0086] FIG. 16 shows linear multi-detector arrangement 56 with detectors 42 according to FIGS. 9 and 10 in a serial arrangement in a flat rectangular container 57, whereby a common connecting cable 58 is used to connect the internal SiPMs to the external signal processing means (not shown).

[0087] FIG. 17 shows an embodiment in which the foil or converter membrane 47 can be self suspended by gluing or welding several foils together in defined points such as to form a multidimensional structure that maximizes converter area while keeping foils sufficiently separated to allow neutron capture products to deposit maximal energy in the scintillating gas in scintillation volume 19 without colliding with an obstacle. Alternatively, such structure may be achieved by cleverly packing self-supporting geometrical shapessuch as small cylinders and conesmade of converter foil.

[0088] The ability to detect and respond to the unauthorized transportation, accidental release or terrorist release of various radioactive materials over a wide area is becoming more and more probable due to the break-up of countries having nuclear weapons and nuclear reactors. Radioisotope smuggling and black market sales of radioactive material has increased substantially in the past years.

[0089] Therefore, the neutron detecting device according to the invention is a valuable tool for being part of a detector network that enables authorities to detect actual locations and moving profiles of such radioactive material. Some proposals in this area have already been made in the past.

[0090] Document US 2014/224964 A1 discloses a system including at least one imager having a pixelated chip that is capable of relaying information regarding the interaction of the high energy particle with the pixel while simultaneously obtaining an image, a central command center with a processor for receiving and interpreting said information from the imager, and for issuing operating instructions to remotely control the imager, and means for communication between the imager and the central command center. The system may also include at least one processor that is in communication with the imager, which is able to determine that a pixel or pixels have interacted with one or more high energy particle.

[0091] Document US 2009/012745 A1 discloses a radiation detection system including many receivers to continuously receive radiation emission data from at least some of a sufficient density of dispersed detectors capable of communicating geo-positions and photon emission counts over a network; the data includes gamma intensities, time stamps, and geo-positions. A processor builds digital image data of the received radiation data for a geographic area by treating gamma-ray proton data from each dispersed detector as a pixel in a low-light image. The processor continuously executes a plurality of statistical computational analyses on the digital image data to separate detected radiation signals from random, undesired signal noise, and known signal noise or sources. The statistical computational analyses include match-filter and/or other convolution techniques.; An interface reports to a user when the computational analyses result in detection of a radiation signal and reports a location of one or more of the dispersed detectors that contribute to the detection.

[0092] Document U.S. Pat. No. 8,502,158 A shows a detection unit for detecting ionizing radiation including a crystal that interacts with incoming radiation; a processing module that analyzes the incoming radiation detected by the crystal; a positioning module that determines position of the detection unit; and a network interface module that receives and transmits time stamped radiation data and position information from/to a plurality of other detection units. The detection unit automatically identifies other detection units that are located close to form a cluster. The detection unit also includes radiation data integration logic that integrates the incoming radiation data from all detectors in cluster, the position of the detection unit, the received radiation data from other detection units and the received position information from other detection units in real time, and process it simultaneously, that allows significantly improve performance and reliability.

[0093] As shown in FIGS. 18 and 19, a neutron detecting device 61 according to the invention may be part of a (e.g. wide area) detector system 60, wherein a plurality of detector subunits 59 are connected with a control center 68 for evaluating detector data, which have been sent to control center 68 via a wireless network 67.

[0094] The neutron detecting device 61 according to the invention may be part of at least one of said detector subunits 59. The subunits 59 may be stationary and/or mobile, i.e. mounted in a car or carried by a person. Within such detector subunit 59 neutron detecting device 61 is connected to a computer, especially a single board computer 62. Single board computer 62 is connected to a network unit 66, which is able to establish a wireless data transmission between subunit 59 and control center 68 via network 67. Single board computer 62 comprises a detector software 63, which is used to monitor detector health and is responsible for neutron counting. Single board computer 62 further comprises a data aggregation software/network protocol 64.

[0095] To determine and transmit the actual position of the detector subunit 59, a GPS unit 65 may be provided, which is connected to said single board computer 62.

[0096] With the neutron detecting device according to the invention it is possible to evaluate the presence, the intensity and/or the type of gamma radiation interacting with the scintillating volume. When accumulating the interaction events of neutrons and Gamma radiation with the scintillation volume over a certain period of time, preferably between 1 and 100 seconds, overlapping energy spectra of Gamma radiation and neutrons, and the accompanying noise are obtained as shown in FIG. 20, where 69 denotes the Gamma energy spectrum and 70 denotes the neutron energy spectrum.

[0097] Analyzing a spectral distribution as shown in FIG. 20 may be done following a scheme according to FIG. 21. The two overlapping spectral distributions 69 and 70 resulting from the simultaneous interaction of Gamma radiation and neutron radiation with the scintillating volume and/or the converter foil are analyzed employing statistical methods.

[0098] In a first step, the Gamma/neutron count rate ratio 71 is determined and results in a certain value k. Then, k is compared to a predetermined reference value p (comparisons 72, 73). If k<, count rates R.sub.II (for Gamma radiation) and R.sub.III (for neutrons) are simply added to give the neutron count rate R.sub.n (74). If k>, a weighted term F(k)R.sub.II is subtracted from the sum R.sub.II+R.sub.III to give the neutron count rate R.sub.n (75). Thus, in this case, the net neutron count rate 75 can be determined by subtracting the spectral response 69 obtained by the gamma radiation from the total spectrum.

LIST OF REFERENCE NUMERALS

[0099] 10,10,10 neutron converter foil (foil, membrane)

[0100] 11,11 substrate

[0101] 12,12 neutron conversion layer (e.g. coating)

[0102] 13,13 wavelength shifting layer (e.g. coating)

[0103] 14,27 scintillation (incident)

[0104] 15 scintillation light (short wavelength)

[0105] 16,16 visible light

[0106] 17 decay product

[0107] 18 neutron (incoming)

[0108] 19,23 scintillation volume (e.g. filled with noble gas)

[0109] 20,20 neutron detecting device

[0110] 21,22 reflector

[0111] 24 converter membrane

[0112] 25 substrate (transparent film)

[0113] 26 transparent LiF coating (on both sides)

[0114] 28 triton

[0115] 29 light sensing device (e.g. Silicon Photomultiplier SiPM)

[0116] 30 signal processing scheme

[0117] 31 detector

[0118] 32 analogue multi-channel front-end unit

[0119] 33 filed programmable gate array FPGA

[0120] 34 power supply

[0121] 35 microcontroller

[0122] 36 cascading scheme

[0123] 37 coincidence unit

[0124] 38,39 channel

[0125] 40 unit cell

[0126] 41 SiPM

[0127] 42 detector

[0128] 43 tube (e.g. steel)

[0129] 43a scintillation volume

[0130] 44 closure head

[0131] 45 valve

[0132] 46 moderating plate

[0133] 46a,b plate element

[0134] 47 converter membrane (double-sided)

[0135] 48 connecting cable

[0136] 49 membrane slot (meandering)

[0137] 50 detector board

[0138] 51 foil reel

[0139] 52 guide rod

[0140] 53 slot

[0141] 54,56 detector arrangement

[0142] 55,57 container

[0143] 58 connecting cable

[0144] 59 detector subunit

[0145] 60 detector system

[0146] 61 neutron detecting device

[0147] 62 computer (single board)

[0148] 63 detector software

[0149] 64 data aggregation software/network protocol

[0150] 65 GPS unit

[0151] 66 network unit

[0152] 67 network

[0153] 68 control center

[0154] 69 Gamma energy spectrum

[0155] 70 neutron energy spectrum

[0156] 71 Gamma/neutron ratio

[0157] 72,73 comparison with reference value

[0158] 74,75 neutron count rate

[0159] A reflective material (e.g. dielectric mirror)