None.
The present approach relates to the advantageous use of BNNT materials, and in particular high-quality BNNT materials, having a second scintillating material. The second scintillating material may be, for example, a scintillating crystalline polymer, and may be coated on the BNNTs, and/or dispersed within the BNNT material. It should be appreciated that some embodiments may include the second scintillating material as a coating on the BNNTs in the BNNT material, and some embodiments may include the second scintillating material dispersed within the BNNT material, and some embodiments may have the second scintillating material as both a coating on the BNNTs and dispersed within the BNNT material.
There are numerous advantages in utilizing high-quality BNNT materials in embodiments of the present approach. For example, with appropriate refining to reduce the content of boron particles to less than 1 wt.%, and in some embodiments below 0.2 wt.%, and in some embodiments removing some of the non-BNNT, BN allotropes to less than 30 wt.% and in some embodiments below 10 wt.%, is that the BNNT materials become optically translucent and allow the light produced by either the scintillating crystals or the BNNT themselves, to reach a photon detector (e.g., a the SiPM or PMT photon detector). In some embodiments, the BNNT material is under vacuum or partial vacuum. However, another advantage of preferred embodiments of the present approach is that the second scintillating material, in crystalline form, is stable in air, and air is transparent to the wavelengths of many scintillating crystals. In some embodiments, the BNNT material comprises an enhanced concentration of 10B in the nanotubes. Boron naturally occurs as stable isotopes 10B and 11B, but 11B makes up about 80% of natural boron. Increasing the relative concentration of 10B to 11B, increases the locations for neutron absorption. For example, in some embodiments at least 50% of the boron in the BNNT material may comprise 10B, and in some embodiments at least 60%, and in some embodiments at least 70%, and in some embodiments at least 75%, and in some embodiments at least 80%, and in some embodiments at least 85%, and in some embodiments at least 90%, and in some embodiments at least 95%, and in some embodiments at least 99%. (Note that unless otherwise stated, a percentage of a component in a material is a weight percentage.) References to the percentage of boron comprising 10B relate to the boron feedstock used to synthesize BNNTs, and thus the isotope content of the as-produced BNNT material. For example, at least 50% of the boron in the BNNT material being 10B means that at least 50% of the boron feedstock used for synthesizing the BNNT material was 10B. The following discussion describes the present approach in the context of various embodiments.
Under the present approach, BNNTs provide a mechanism to distribute 10B in a low atomic number, scintillating material.
With reference to the embodiment shown in
The 11B* state lasts about 10-12 seconds. The gamma, when present, comes from the decay of an excited state of 7Li. The total ionization energy available is either 2.31 MeV (94%), assuming no absorption of the gamma, or 2.80 MeV (6%).
In some embodiments, detection of 4He ion 14 and 7Li ion 15 produced in the neutron 11 absorption on 10B 12, the Event, can be achieved in a two-step process: 1) surround BNNTs in the BNNT material 13 and any boron, amorphous BN, and h-BN impurities, with a second scintillating material 16 (e.g., a solid, gas or liquid scintillator), such that as the 4He 14 and 7Li 15 ions lose energy through ionization in the second scintillating material, light is emitted along the ionization path 17; and 2) collect the emitted light and convert it to an appropriate electronic signal (photon detector not shown). The second step is generally known in the art, and suitable techniques and apparatus for collecting light, converting the light to an electronic signal, and measuring the signal are available to the person having an ordinary level of skill in the art. However, the embodiments described below provide improved light collection relative to contemporary alternatives. The second scintillating material 16 can be a solid, liquid, or gas. In the preferred embodiment discussed herein, the second scintillating material is a crystal coating and, in some embodiments, dispersed within the BNNT material. The 4He ions 14 and 7Li ions 15 may lose some of their energy in the BNNT material 13 with its boron, amorphous BN, and h-BN impurities, in addition to losing energy in the second scintillating material. In some embodiments, the thermal neutron detector may be designed such that most of the ionization occurs in the second scintillating material, and relatively small amounts of the ionization occur in the BNNT material 13 itself by having the mass of the second scintillating material higher than the mass of the BNNT material. The ratio of ionization in the BNNT material compared to the second scintillating material is controlled by the ratio of the respective masses of material present with some adjustment for the atomic numbers of the materials.
As seen in the geometry of
Embodiments of the present approach may use various types of BNNTs, although embodiments using high quality BNNT material will have the greatest signal detection due to their optical transparency. BNNT, LLC (Newport News, Virginia) produces high quality BNNT material by high temperature, high-pressure (HTP) methods that may be used in embodiments of the present approach. The synthesis processes are catalyst-free, and the processes only use boron and nitrogen gas as feedstock. The BNNTs in high quality BNNT material have few defects, 1- to 10-walls with the peak in the distribution at 2-3-walls and rapidly decreasing with larger number of walls. BNNT diameters in these materials typically range from 1.5 to 6 nm, and they may extend beyond this range. Nanotube lengths in these materials typically range from a few hundreds of nm to hundreds of microns, and they may extend beyond this range.
The following paragraphs refer to as-produced BNNT material, which as used herein refers to the high quality BNNT material available from BNNT, LLC. For the as-produced BNNT material, the composition of the material greatly depends on the synthesis parameters and is mixture of high quality BNNTs, boron particles, amorphous boron nitride (a-BN), hexagonal BN (h-BN) h-BN nanocages, and h-BN nanosheets. The non-BNNT components of the as-produced material are typically a few 10 s of nm in size or less (e.g., about 10 to about 50 nm, and in some embodiments, about 20 to about 50 nm, and in some embodiments, about 30 to about 50 nm, wherein the term “about” in this context means +/- 0.3), but they may extend beyond this range. The production parameters of the HTP process can be adjusted to have more or less boron as compared to the a-BN and h-BN species.
The as-produced BNNT material is approximately 0.5 grams per liter (0.5 g/L), and may vary by +/- 50%. This value of the “tap density” can be compared to the density 2,100 g/L for h-BN. The as-produced BNNT material has the appearance of a “cotton ball” or “puffball.” BNNT material can equally well be made with natural boron or 10B or 11B. In some embodiments, the BNNT material includes an enhanced concentration of 10B in the nanotubes. For example, BNNT, LLC (Newport News, Virginia) produces 10B-containing BNNT material, utilizing 96 wt.% enriched boron feedstock. It should be appreciated that an enhanced concentration of 10B may have more than 25% 10B, more than 30% 10B, more than 35% 10B, more than 40% 10B, more than 45% 10B, more than 50% 10B, more than 55% 10B, more than 60% 10B, more than 65% 10B, more than 70% 10B, more than 75% 10B, more than 80% 10B, more than 85% 10B, more than 90% 10B, or more than 95% 10B, all by weight. This specification refers to a BNNT material having an enhanced 10B concentration as 10BNNT, for shorthand. It should be appreciated that various levels of 10B-enriched feedstock are available, and other fractions may be used without departing from the present approach.
The puffball form-factor of 10BNNT has been useful for initial prototyping, but may have structural limitations for some embodiments of radiation and thermal neutron detectors. Further, boron particles in the BNNT material are preferably removed, because they are absorptive of the wavelengths of light of interest. Various purification or refinement processes can be used to remove (which, as used herein, includes significantly reduce the amount of) boron particulates in a high quality BNNT material, including those disclosed in International Patent Application No. WO 2018/102423 A1, filed Nov. 29, 2017, and incorporated by reference in its entirety. Generally, reducing the residual boron particle content of a BNNT material will improve the BNNT material’s use as a scintillator. In some embodiments, residual boron particles remaining after purification comprise less than 20 wt.% of the BNNT material, and in some embodiments the residual boron particles comprise less than 10 wt.% of the BNNT material, and in some embodiments the residual boron particles comprise less than 5 wt.% of the BNNT material, and in some embodiments the residual boron particles comprise less than 1 wt.% of the BNNT material, and in some embodiments the residual boron particles comprise less than 0.5 wt.% of the BNNT material. Further, the refining process can also be tuned to additionally remove the majority of a-BN, and if desired, some of the h-BN nanocages and h-BN nanosheets, particularly along their edges and near any defects. Unlike other refinement processes in the art, the refining processes referenced herein are not acid-based and do not introduce any metals into the final BNNT material. The following description refers to the as-synthesized BNNT material as Beta, the BNNT material with boron particles removed (i.e., at least under 20 wt.%) as Gamma or R, and the BNNT material with some removal of BN allotropes as Zeta or RX.
Three different forms of the as-synthesized 10BNNT material from BNNT, LLC (Newport News, Virginia) are described herein. First, the P1 series represents the original, as-produced BNNT material. The P2 series represents a tradeoff of having more boron particles but significantly less h-BN nanosheets. The SP-10 series is similar to P2, except it is produced by a high-throughput HTP process. The initial 10BNNT scintillation results reported below are with P1-Beta BNNT material where the Beta label indicates that the material was not refined to remove any of the boron particles.
With respect to BNNT material form-factors suitable for the present approach, a wide variety may be used, ranging from as-produced puff-balls, to BNNT mats, and BNNT buckypapers. BNNT buckypapers are well-suited for many embodiments of the present approach. A BNNT buckypaper may be formed through dispersing BNNT material in a solvent, filtering the BNNT dispersion, collecting BNNTs on a filter, and drying the solvent to form a solid BNNT buckypaper on the filter. BNNT buckypapers have been manufactured in a wide range of sizes, and from all the various BNNT materials referenced herein (e.g., P1, P2, SP-10, Beta, Gamma, and Zeta, R, and RX). The BNNT buckypapers used in various embodiments have a thickness from 10 to 200 microns. For an areal density near 1 mg/cm2, the thickness is typically 10-20 microns, but other embodiments may extend beyond this range. For a BNNT buckypaper placed under high compressive force, the compressed thickness can become as low as 0.7 microns, however the BNNT buckypapers used in the embodiments discussed herein were not under external pressure. A 10 micron 10BNNT buckypaper is typically near 1 mg/cm2, and absorbs 10% of the thermal neutrons impacting the surface.
Various prototypes employing BNNT buckypapers have been evaluated. BNNT buckypapers having diameters of 3.5 cm and 7 cm were used in many of the prototypes, but other dimensions may be used in other embodiments.
The following paragraphs discuss four demonstrative approaches to introduce scintillating crystals 42 to the BNNT material. It should be appreciated that the person having an ordinary level of skill in the art may use an alternative approach to coat on, and/or disperse within, a second scintillating material to a BNNT material. In a first example, a crystal precursor material may be placed into a solution into which the BNNTs have been dispersed. Using anthracene as an example, anthracene may be dispersed into organic solvents such as ethanol and isopropyl alcohol (IPA), and then BNNTs may be stirred into the solution. Anthracene, a preferred second scintillating material in the present approach, has the highest scintillation light output of any organic scintillator for a given level of ionization. Depending on the BNNT material’s form-factor (e.g., whether the BNNTs are in a puffball or powder), the level of stirring or sonication of the mixture will vary as those of ordinary skill will appreciate. The mass ratio of scintillating precursor and BNNT material can be varied depending on the embodiment and the balance of ionization loss of the 4He and 7Li ions as discussed above. Typically, the mass ratio varies by at most a factor of two, but embodiments beyond this range can also be utilized if the ratio benefits the propagation of the light through the crystal-coated BNNT material. For example, anthracene will dissolve at 2 grams per liter of ethanol at room temperature, and 2 grams of BNNT material can be readily dispersed in ethanol by robust stirring of BNNT material, either as puffballs or powders. The anthracene-BNNT-ethanol mixture can then be placed on a target surface, such as a metal or plastic surface. In some embodiments, the surface may be a mold to shape the crystal-coated BNNT material into a desired form factor. The ethanol solvent may be removed, such as through evaporation, leaving an anthracene crystals coating on the BNNTs, and dispersed within the BNNT material. The process can be repeated multiple times on a surface, if desired, to produce the specific thickness of crystal-coated BNNT material layers.
In second method of introducing the second scintillating material to BNNTs, a crystal precursor material in solution may be introduced to a BNNT buckypaper. In this method, a BNNT buckypaper is prepared from the BNNT material as described above and illustrated in
In the third demonstrative method of introducing a second scintillating material to BNNTs, the scintillating crystals are dry mixed into the BNNT material through one or more processes such as milling and robust stirring in a blender. This process may have advantages for shaping the scintillator materials into desired form-factors, and for working with second scintillating materials that do not readily go into solution, such as thallium-doped sodium iodide that may lose the thallium in the water typically used to dissolve sodium iodide, or such as cerium doped lutetium aluminum garnet (Ce:LuAG) ceramic that is formed at temperatures in excess 1700° C. and does not dissolve into solvents. Other non-limiting examples of second scintillating materials are described below. A potential disadvantage of this method, for some embodiments, is that the resultant material may not be adequately transparent to efficiently get the scintillation light to the photon detection components of the detector apparatus.
A fourth demonstrative method of introducing a scintillating material to a BNNT material is a variation on the first method, and is a preferred method for some embodiments. Anthracene is dissolved by stirring into IPA, or another solvent such as ethanol, methanol, hexanes, acetone, chloroform, or diethyl ether, at a level to be within 30 wt.% of its saturation for the temperature being utilized (e.g., often room temperature). BNNT material is separately placed into the same or a compatible solvent, which may be IPA, ethanol, methanol, hexanes, acetone, chloroform, diethyl ether, or another appropriate solvent, and then stirred for a sufficient time to breakup and suspend the BNNT puffballs or other starting material (e.g., for about 50 hours, about 60 hours, about 70 hours, about 80 hours, about 90 hours, or about 96 hours, or about 100 hours, wherein “about” in this context means +/- 2 hours). The solution of BNNT starting material may then be subjected to another mechanical dispersion technique, including, but not limited to bath sonication or probe sonication. There is typically 0.01-2 mg of BNNT material per mL of solvent. The dispersion of BNNT material and the anthracene solution are then combined at a target ratio of mass of BNNT to anthracene in the mixture (e.g., 1:1 to 1:2, although other ratios may be utilized depending on the desired result). Next water, or another solvent in which the anthracene is immiscible (typically <0.5 mg/mL at the temperature of interest), is added dropwise to the mixture of BNNT, anthracene, and IPA of sufficient quantity to precipitate the anthracene with stirring. The mixture is then stirred sufficiently to allow crystal formation (e.g., from 50 to 100 hours, such as about 50 hours, about 60 hours, about 70 hours, about 80 hours, about 90 hours, or about 100 hours, or about 96 hours, wherein “about” in this context means +/- 2 hours). As those of ordinary skill in the art will appreciate, the mole fractions, rates of solvent introduction, and temperature will affect the size and quality of the crystals in the solution-based crystal growth methods. Testing in the parameter space discussed above has shown that introducing water at a wt.% ratio of 2:3 within 15 seconds to a minute will generate anthracene crystals typically less than 5 microns in size with most of them below 1 micron in size that work for generating light in a neutron detector. Vacuum filtration may then be utilized for extracting the mixture of BNNT material, anthracene, and anthracene-coated BNNT material, resulting in a BNNT buckypaper having a crystal coating and crystal dispersed within the BNNT material. The thickness of the BNNT buckypaper prepared using this approach is in the range of 10-100 microns, and the volumetric density is in the range of 0.1-0.8 g/cm3 but may extend beyond these ranges in other embodiments. It should be appreciated that this approach, utilizing anthracene, will work for other second scintillating materials may be precipitated in solution with the use of appropriate solvent systems.
There are a variety of scintillator materials that may be used as a second scintillator material. With respect to organic crystals, many are aromatic hydrocarbons having benzene rings in various interlinked patterns. Examples of organic crystal scintillators include anthracene, stilbene, and naphthalene. Anthracene has been used in the example discussed herein because as discussed above it generates more light for a given level of deposited ionization than any other organic scintillator, and it has been used in initial testing because it readily dissolves in ethanol and IPA and is easy to work with in the lab environment. However, there are more the twenty other commonly used organic scintillators and roughly the same number of inorganic scintillators that can be utilized, such as those available from Hilger Crystals (Concord, MA), and Saint-Gobain Crystals (Milford, New Hampshire). Other examples include Bismuth Germanate (BGO) -Bi4Ge3O12, Cadmium Tungstate - CdWO4, CLYC - Cs2LiYC16(Ce), Europium-doped Calcium Fluoride - CaF2(Eu), GLuGAG - (Gd,Lu)3,(GaAl)5,O12(Ce), Lutetium Yttrium Silicate (LYSO), Sodium-doped Caesium Iodide - CsI(Na), Sodium Iodide - NaI, Thallium doped Caesium Iodide - CsI(Tl), Thallium doped Sodium Iodide - NaI(Tl), Yttrium Aluminium Garnet (YAG), Yttrium Aluminium Perovskite (YAP), and Zinc Tungstate. It should be appreciated that the third method for forming crystal-coated BNNT scintillating materials described below may be appropriate for these inorganic crystal scintillating materials. Anthracene may not be preferred for environments where the crystal-coated BNNT material will need to be in ultra-high vacuum (UHV) such as in a particle beam line in an accelerator, or the materials will need to be at high temperature such as in a down-hole drilling system that may be kilometers below the surface. Fortunately, BNNT material survives to over 700° C. in most environments and frequently to much higher temperature, e.g. 1500° C., in some environments such as vacuum or nonreactive gases such as argon and nitrogen. Consequently, scintillating crystals appropriate for these environments can be utilized and higher temperature growing systems such as vapor deposition can be utilized or the mixing methods discusses above as the third method which may be appropriate for when a ceramic scintillator is used for the crystal-coating of the BNNT material. An addition comment on anthracene, is that it works well in air and any other environment where it does not chemically interact. This aids in the manufacturability of detectors.
The thermal neutron cross section area (TNCSA) of one mole of 10B (10 g) is 6.022x1023 atoms/mol × 3835 barns/atom = 0.23 m2/mol where 1 barn = 10-28 m2. For comparison, the 3He TNCSA is 0.32 m2/mol. High quality BNNT material will be more cost-effective than 3He, based on at least the amount needed for a square meter. Additionally, 10BNNT material can be more efficiently deployed. Thermal neutron detectors are frequently rated by cps/nv (counts per second per a flux of 1 neutron per square centimeter second). Using this metric, simply increasing the size of the detector increases the cps/nv rating. A thermal neutron efficiency rating, TNE, for the utilization of the material can be developed by dividing the cps/nv rating by the TNCSA required to achieve this rating. By this TNE rating, based on available information, typical cylindrical 3He detectors have a TNE of 4,635 to 4,676 for the 2.7 atm detectors (ones that can be easily shipped because their internal pressure is below 40 psi (276 kPa) a limit for transportation safety in some countries). The high pressure 3He detectors only have TNE ratings of 3,334 at 10 atm 3He and 1,795 for 20 atm 3He. This lower performance at high pressure is because the 3He gas as the center of the detectors is shielded by the gas near the surface. The TNE rating for manufacturable 10BNNT thermal neutron detectors according to the present approach will be above at least 5,000.
The detector geometry used for the initial testing of anthracene based crystal-coated BNNT material is illustrated in
The following paragraphs describe prototype neutron testing. The ADC used was a CAEN DT5730. The photo detectors were a SensL ArrayC-60035 quad SiPM and a Hamamatsu R6094 PMT. Both are sensitive to blue photons. The source of neutrons for these tests was an AmBe source plus natural background. Cosmic ray interactions with the atmosphere and materials near the surface of the earth are the primary source of thermal neutrons on the surface of the earth. This thermal neutron flux is estimated at 7 neutrons/m2/s for Newport News, VA but can vary significantly and beyond this range depending on surrounding material, elevation, latitude and other location specific conditions. The natural background was anticipated to contribute 0.4 counts per minutes (CPM) for the PMT configuration tested. The AmBe source was not calibrated, so all of the measurements are relative. The detectors were shielded by a combination of iron, lead and tungsten shielding to eliminate the gamma ray background from the AmBe source. Three amounts of high density polyethylene (HDPE) were placed around the detectors to thermalize the epithermal and fast neutrons from the AmBe source: 0”, 1” and 2”. For the PMT the measured rates are shown in Table 1.
The PMT detector efficiently detected the thermal neutrons as indicated by the variation of observed rate with the thickness of the HDPE that thermalized the neutrons from the AmBe source. There was a background in the overall system as observed by the 7 CPM of the no source rate being above the anticipated natural background rate. The full width at half max of the pulses observed were typically between 10 and 20 nanoseconds. This points to sub-10 nanosecond coincidence capabilities for segmented detectors with multiple Events.
The anthracene crystal-coated BNNT material in the SiPM detector system was less than about half of the amount of crystal-coated BNNT material used for the PMT system and covered roughly one third the area with about half the amount of 10B present. The SiPM used had a very high noise rate in each of the four elements of the quad SiPM so they were put in coincidence utilizing constant fraction discrimination. At least two of the four elements had to have a signal to indicate an Event. The coincidences occurred within a 10 nanosecond window. To determine the base rate from the random coincidences between the elements of the SiPM, the SiPM was covered so it could not collect light from the surroundings, and under these conditions it counted at 119 CPM. This rate was dependent on the bias voltage applied to the SiPM. The challenge of high noise rates in SiPMs is well known by those of ordinary skill in working with them, and future planned work will be with SiPMs that are far less noisy for this application.
Table 2 shows the SiPM results. The Event rate was near a factor of four below that of the PMT rate. This is very roughly a factor of two below the anticipated rate. The discrepancy is believed to be mostly a factor of the issue of noise discussed above in the system as the Event rates were a factor of more than ten below the noise coincidence rate. The half width of the pulses observed was near 100 nanoseconds. Again, the SiPM system was not well optimized for the measurement and while the timing was better than 10 nanoseconds, the pulse widths would ideally be narrower. However, the pattern seen with the PMT of the variation in rates between, 0”, 1” and 2” of HDPE was well observed.
While PMTs, as demonstrated, can be used as effective detectors of thermal neutrons in the crystal-coated BNNT material, they have disadvantages of being relatively large and heavy, and they require high voltage, e.g. typically 500 to 1000 volts, and too much power. SiPMs are small, require less than 100 V (typically only 25 V to 50 V) and operate at low power. Both PMTs and SiPMs can have sub 10 nanosecond timing capabilities. However, SiPMs while having good sensitivity to photons also have a higher level of noise than PMTs as discussed above.
The rise time sensitivities of both PMTs and SiPMs is less 10 nanoseconds. The recovery times is dominated by the scintillation times of the crystals employed and the capacitance of the SiPM on the inputs of the preamplifiers. Using anthracene as the crystal scintillating material, the total times of the pulses is well under several hundred nanoseconds. Consequently, maximum detection rates can approach 1 MHz. Some scintillating crystals have much longer decay times and the maximum detection rate will be less.
The full range of measurements planned in 2020 were interrupted by the pandemic, but measurements with SiPMs discussed above with the geometry illustrated in
In addition to improving the scintillating materials, another aspect of achieving a successful neutron detector under the present approach is to optimize the collection and transport of the light from the scintillating process to the SiPM or PMT. Fiber optic side-glow cables are typically used for specialty lighting where typically an LED is placed on the end of a frosted or surface modified fiber optic cable and light is emitted along the frosted section. In some embodiments, an inverse version of this configuration may be used, wherein a fiber optic cable has a frosted section, or partially frosted section and light flows from the frosted section of the cable to the unfrosted end of the cable. These cables may be made of glass, or polymers such as PMMA, polystyrene, or other materials that have high, if not total, internal reflection. This embodiment is referred to as the fiber optic inverse side-glow (FOIS) arrangement. For the light that goes into the frosted section, a portion of this light enters the unfrosted section of the cable as a totally internally reflected and transported stream of photons and it can be detected by a photo detector such as a SiPM or PMT. With the copious amounts of light observed from Events in the crystal-coated BNNT material, such embodiments are practical. Some thermal neutron detection requirements benefit from submillimeter resolution of the Event location or for large area detectors centimeter and beyond resolution. With crystal-coated BNNT material being the source, location of the thermal neutron Event becomes possible in the FOIS arrangement.
The geometries of the FOIS cables illustrated in
When the total of the crystal-coating on the BNNT materials is near 11 mg/cm2 for the content of BN allotropes including BNNTs, the thickness will be near 0.5-1 mm, not including the FOIS cables. At this areal density roughly 63% of the thermal neutrons impacting on detector will result in Events. If the thickness of the BN allotropes is doubled (or, in some embodiments, tripled), then the Event efficiency will increase to near 87% (or 95%). Consequently, while large surfaces, e.g. meters squared and larger may be covered by the detector, the thickness can be made as thin as a few mm (e.g., about to about 5 mm, or in some embodiments, about 2 to about 5 mm, or in some embodiments, about 3 to about 5 mm, wherein the term “about” in this context means +/- 0.3). This can be important for making large area portal monitors, space radiation detectors and some scientific measurements. Additionally, the materials can be at atmospheric pressure, as well as above and below this pressure, and the materials are lightweight and nontoxic. If high temperatures are required such as in down-hole systems, the crystals can be inorganic, the FIOS cables can be glass, and the cables can be multiple kilometers in length so that the temperature sensitive photo detectors are at ground/surface levels. Additionally, as discussed above the Events can be timed to less than 10 nanoseconds when this is important for the specific application.
If three of these relatively thin crystal-coated BNNT material FOIS cable layers are made into planes, then directional detectors can be created by having the three planes orthogonal to each other. With this geometry the source direction(s) can be determined. For example, this may be useful for satellite applications observing the surface of the Earth. If hydrogen rich layers of a material a few centimeters thick (e.g., about 1 to about 5 cm, and in some embodiments, about 2 to about 5 cm, and in some embodiments, about 3 to about 5 cm, wherein the term “about” means +/- 0.2), such as HDPE, are placed in between and outside the layers in the planes of the layers, then fast neutrons are both attenuated and moderated to become thermal neutrons. A mapping of Events that can be used to determine the direction of the source of fast neutrons in applications such as portal monitors and satellite observations.
It should be appreciated that the previous discussion identified numerous embodiments of the present approach. Indeed, a number of geometries are possible with this technology:
The present approach may be embodied in forms other than as disclosed in the various embodiments, as will be appreciated by those having an ordinary level of skill in the art. The present embodiments are therefore to be considered in all respects as illustrative and not restrictive.
Filing Document | Filing Date | Country | Kind |
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PCT/US2021/014288 | 1/21/2021 | WO |
Number | Date | Country | |
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62963828 | Jan 2020 | US |