METHOD FOR DETERMINING THE NEUTRON FLUX BY USING A PORTABLE RADIONUCLIDE IDENTIFICATION DEVICE (RID) COMPRISING SCINTILLATION MATERIAL WITH IODINE

Abstract

A method for determining neutron flux by utilizing a portable Radionuclide Identification Device (RID) as it is used in homeland security applications is provided. The RID has an inorganic crystal comprising iodine, a light detector and electronics for the evaluation of the output signals of the light detector. The method includes a step of detecting, with the light detector, light emitted by the crystal following the interaction of nuclear radiation with the crystal. The intensity of the light measured is a function of the energy deposed in the crystal by said nuclear radiation during the interaction with the crystal.

Claims

1-10. (canceled)

11. A portable radionuclide identification device (RID), comprising: an inorganic crystal adapted to emit light in response to radiation induced interactions; a light detector adapted to capture said light emitted by the inorganic crystal and generate an output signal; and electronics in communication with the light detector and configured to determine a neutron flux based on the output signal, wherein the electronics are adapted to: evaluate a characteristic of the output signal to determine an amount of energy deposited in the inorganic crystal by the radiation induced interactions; identify a first set of events in a first energy range and a second set of events in a second energy range, wherein the first energy range and the second energy range are different; determine a first count rate for the first set of events and a second count rate for the second set of events; determine a background count rate that is indicative of cosmic radiation interactions with the inorganic crystal; and determine the neutron flux based on the background count rate and second count rate.

12. The portable radionuclide identification device (RID) of claim 11, wherein the electronics are further adapted to determine the background count rate by determining an expected count rate indicative of an expected number of interactions between the inorganic crystal and cosmic radiation within the second energy range.

13. The portable radionuclide identification device (RID) of claim 12, wherein the electronics are further adapted to determine the expected count rate based on the first count rate and a known energy distribution of cosmic radiation.

14. The portable radionuclide identification device (RID) of claim 11, wherein the electronics are further adapted to determine the neutron flux by subtracting the background count rate from the second count rate.

15. The portable radionuclide identification device (RID) of claim 11, wherein the first energy range comprises energies that exceed a first threshold energy value.

16. The portable radionuclide identification device (RID) of claim 15, wherein the first threshold energy value is approximately 10 MeV.

17. The portable radionuclide identification device (RID) of claim 15, wherein the first threshold energy value is defined such that, in the first energy range, the majority of the events originate from interactions with cosmic radiation.

18. The portable radionuclide identification device (RID) of claim 11, wherein the second energy window comprises energies above a second threshold energy value and below a third threshold energy value, wherein the third threshold energy value is less than or equal to the first threshold energy value.

19. The portable radionuclide identification device (RID) of claim 18, wherein the second threshold energy value is approximately 3 MeV.

20. The portable radionuclide identification device (RID) of claim 18, wherein the second threshold energy value is higher than a maximum energy expected to be deposed by the radiation.

21. The portable radionuclide identification device (RID) of claim 20, wherein the third threshold energy value is approximately 5 MeV.

22. The portable radionuclide identification device (RID) of claim 11, wherein the inorganic crystal comprises iodine.

23. The portable radionuclide identification device (RID) of claim 11, wherein the inorganic crystal is selected from a group comprising sodium iodide and cesium iodide.

24. The portable radionuclide identification device (RID) of claim 11, wherein the characteristic is a pulse height of the output signal.

25. The portable radionuclide identification device (RID) of claim 11, wherein the electronics are further adapted to correct the background count rate by adding a count rate of pileup events within the second energy range.

26. The portable radionuclide identification device (RID) of claim 25, wherein the count rate of pileup events is calculated by multiplying a calculated pileup count rate in the second energy range with a mean count rate and a pulse pair resolving time.

27. The portable radionuclide identification device (RID) of claim 26, wherein an expected count rate of pileup events is calculated from a count rate of events built by the sum of two consecutive random events in the second energy range.

28. The portable radionuclide identification device (RID) of claim 11, wherein the electronics are further adapted to determine a neutron flux count rate based on the background count rate and second count rate and determine the neutron flux from the neutron flux count rate.

29. The portable radionuclide identification device (RID) of claim 11, wherein the electronics are further adapted to generate an alarm when the neutron flux count rate exceeds a threshold value.

30. The portable radionuclide identification device (RID) of claim 29, wherein the electronics are further adapted to determine the threshold value from the background count rate within a predetermined time.

Description

BRIEF DESCRIPTION OF THE DRAWINGS

[0018] An embodiment of the invention is described, referring to

[0019] FIG. 1 showing a measured background spectrum in the energy domain (energy spectrum) with an extended energy range up to 1 GeV, and

[0020] FIG. 2 showing two measured spectra in the energy domain with an extended energy range of up to 100 MeV, namely a background spectrum with and without additional neutron source.

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0021] The inventor found that the relevant events can be separated into three regions of interest (ROI), separated by the energy deposed in the crystal. The first ROIROI()covers energies up to 2.6 MeV In this region, events originating from external gamma radiation (gamma events) dominate. It is the main purpose of an RID to evaluate those gamma events and to determine the origin of the gamma radiation source on the basis of the energy and the distribution of said gamma events. Other than a detector used for example in nuclear research, an RID only needs to detect gamma events originating from natural sources. Embodiments of the invention therefore makes use of the fact, that there is more or less no gamma radiation from natural sources, i.e. from decaying nuclei, with gamma energies of more than 2.6 MeV. Being more exact, the highest gamma energy expected from such sources is E().sub.max=2,615 MeV (2.615 keV). The inventor also found that the sum energies, that is the sum of one or more gamma quanta being emitted from excited states coincidently, of gamma events from relevant coincident decays, i.e. from .sup.60Co or .sup.137Cs, is smaller than 2.6 MeV also when originating from natural sources.

[0022] As a consequence, an event with energies above 2.6 MeV, preferably above 3 MeV, measured by an RID, can be treated as not originating from external gamma radiation, but from heavy particles like neutrons, protons or muons, interacting with the crystal only. In order to be able to evaluate events with energies above 2.6 MeV, the electronics controlling the RID needs to be modified in a first step, enabling the RID to detect and to evaluate events with energies above 2.6 MeV. A standard RID is not set accordingly as the crystal is only used to detect gamma radiation events from natural sources, i.e. events with energies lower than 2.6 MeV.

[0023] Some neutrons will be captured by the iodine nuclei present in the crystal. This will lead to excited states in iodine which will decay to ground level by emitting gamma radiation, said gamma radiation having sum energies starting at around 2.6 MeV, mostly in the energy range between 3 and 8 MeV with a significant peak between 3 and 5 MeV.

[0024] The mean energies of muons at the earth's surface is around 4 GeV. Those muons will deposit an energy in the order of 4 MeV/cm in the crystal. For a diagonal trajectory in an 55 cm NaI crystal, the maximum energy deposed would be in the order of 28 MeV. However and due to other effects, muons will deposit up to 200 MeV of energy in the crystal (muon energy E()).

[0025] As a consequence, events with measured energies of E.sub.T1=10 MeV and above are more or less solely events, originating from interactions between cosmic radiationmainly muons ()and the crystal, whereas events with energies above E().sub.max=2,615 MeV and below E.sub.T1=10 MeV may originate from either neutron events or muon events. Those thresholds define the next two ROIs of relevance here: ROI() is the region above event energies of 10 MeV, that region dominated by interactions of muons with the crystal. The third ROI, ROI(n, ), is the region between a second threshold E.sub.T2 and a third threshold E.sub.T3, E.sub.T2 being larger or equal E()max and a third threshold E.sub.T3, being lower or equal the first threshold E.sub.T1 but higher than E.sub.T2.

[0026] In the present embodiment, E.sub.T1 is set to 10 MeV, E.sub.T2 to 3 MeV and E.sub.T3 to 5 MeV. FIG. 1 shows the resulting energy spectrum measured overnight without a radiation source, using a RID with a NaI(Tl) crystal, the crystal having a standard size of 22 inch and set to detect and evaluate events with energies up to 1 GeV. The region with energies above E.sub.T1=10 MeV, ROI(), is marked with C. The ROI(n, ) region between E.sub.T2 and E.sub.T3 is marked with B1 and covers the region between E.sub.T2=3 MeV and E.sub.T3=5 MeV, the gap between 5 and 10 MeV is marked with B2. Setting such a gap ensures a clear separation of the events.

[0027] The events below E.sub.T2=3 MeV are gamma events, resulting from background radiation.

[0028] FIG. 2 shows two measured spectra with an RID, comprising a 2 inch2 inch NaI(Tl) crystal, set to detect and evaluate events with energies up to 100 MeV. Spectrum 100 is again a spectrum showing the background radiation, whereas spectrum 200 shows a background spectrum with a neutron source present in addition. Region A in FIG. 2 again covers energies up to 3 MeV, therefore showing the background gamma events. Region C, the ROI(), covers energies between about 7 MeV and 100 MeV, i.e. the region where cosmic (muon) radiation begins to dominate. Region B between 3 MeV and about 7 MeV is covering the neutron capture region, where cosmic radiation is present in addition, i.e. the region ROI(n, ).

[0029] It can be seen from FIG. 2 that the count rates in regions A and C are more or less identical in the two spectra 100 and 200, whereas a significant difference can be seen in region B. The events measured in region B are, as far as the background of spectrum 100 is concerned, cosmic muons and, in spectrum 200, the sum of neutron- and muon-events.

[0030] It has to be mentioned further that the spectrum shown in FIG. 2 has been collected over several hours, therefore providing good statistics which allows to clearly distinguish between spectra 100 and 200 in region BROI(n, ). During real measurements with an RID, the RID has to issue an alarm within seconds and therefore has to use spectra with significant fewer events. As a consequence, spectra 100 and 200 would hardly be distinguishable if compared like in FIG. 2.

[0031] In order to quickly determine the neutron count rate as required for an RID in a spectrum measured like spectrum 200, the measured count rate has to be corrected by the background count rate, i.e. the muon count rate.

[0032] As an RID is to be used in different surroundings with changing background count rate, it is not possible to determine the background radiation in advance in a separate measurement as one would do in a laboratory or when using a non-portable detector. Therefore, the total height of the muon induced background events in ROI(n, ) is, like the corresponding background count rate R(n, ), unknown, as they are dependent at least from the position of the RID and the time in the year, as the muon intensity is varying over the year.

[0033] Embodiments of the invention make use of the fact that the energy distribution of the muons interacting with the crystal is known and can be calculated for the region ROI(n, ) for each crystal. The events within ROI() are deemed to be muon events only. The same is true for the respective count rate R(). With the knowledge of the number of muon events in ROI() over a predetermined timethe muon count rate R() in ROI()and the muon energy distribution in the NaI(Tl) crystal used, the number of expected muon events in ROI(n, ) over timethe expected muon count rate R().sub.exp in ROI(n, )can be calculated. Subtracting this number from the total count rate R(n, ).sub.total of events in ROI(n, ) provides the number of neutron events over time, i.e. the neutron count rate R(n) which is a measure for the actual neutron flux:

[00001]$\begin{array}{cc}R\left(n\right)={R\left(n,\right)}_{total}-{R\left(\right)}_{\exp }& \left(1\right)\end{array}$

[0034] As the detection efficiency for neutrons can be easily determined for a specific RID in advance, the actual neutron flux can be determined from the measured neutron count rate R(n). The RID according to this embodiment will issue an alarm as soon as the neutron count rate R(n) increases above a predetermined value.

[0035] The measurement of the neutron count rate R(n) can be further improved when pileup information is taken into account also. Known means against pileup are count rate limitation and a tight pileup rejection with minimum pulse pair resolution time t.sub.ppr, but there will still be an inevitable statistical pileup which cannot be avoided completely.

[0036] The RID of the preferred embodiment is using state of the art pulse processing for the evaluation of the events measured, namely pulse height discrimination (PHD) for distinguishing gamma radiation from neutron capture events from other events. When the count rate of events is high, pulse pile up may occur so that pile up events originating from several different gamma events within a small time window, so called random coincidences, may look like events with higher energies. Some of those will increase the number of events in ROI(n, ) without originating from interactions with neutrons and/or muons, thus increasing the measurement error.

[0037] The inventor used statistical considerations, making use of the fact that the emission of gamma quanta is Poisson distributed. A pileup occurs when the time between two pulses is shorter than the pulse pair resolving time t.sub.ppr of the detector, here the portable RID. In order to estimate the pileup rate in the neutron capture region, that is in ROI(n, ), one has to know the total (artificial) coincidence probability and the sum spectrum energy distribution.

[0038] This pileup can be estimated by creating an artificial sum spectrum from the measured gamma events. This sum spectrum is set up by adding the energies of two consecutive events and creating a new spectrum from those summed up events only. The rate of sum events measured in ROI(n, ), that is the rate of sum events with E.sub.T2<E(sum)<E.sub.T1, is R(n, ).sub.sum. A good estimation of the rate of false pileup events caused by statistical pileups in the region ROI(n, )R(n, ).sub.pileupcan be calculated by scaling that rate of sum events by r t.sub.ppr, r being the mean count rate:

[00002]$\begin{array}{cc}{R\left(n,\right)}_{\mathrm{pileup}}-{R\left(n,\right)}_{sum}*{\mathrm{rt}}_{\mathrm{ppr}}& \left(2\right)\end{array}$

[0039] In order to further correct the measured count rate of neutron events, it can be further corrected by taking the estimated pileup count rate within ROI(n, ) into account also:

[00003]$\begin{array}{cc}R\left(n\right)={R\left(n,\right)}_{total}-\left({R\left(\right)}_{\exp }+{R\left(n,\right)}_{\mathrm{pileup}}\right)& \left(3\right)\end{array}$

[0040] It has to be mentioned that both, R(n, ).sub.sum and r, are obtained from actual measurement data during the measurement in real time so that this further correction is accurate and adapted to the actual measurement situation.

[0041] Whereas embodiments of the invention relate to the evaluation of events with energies above E().sub.max, it goes without saying that the portable RID described herein is at the same time capable of measuring gamma radiation with energies below E().sub.max and to evaluate those in order to identify the radionuclides being the source of said gamma radiation. Those events lying in the ROI() are evaluated in parallel according to standard evaluation methods for gamma radiation detected with RIDs so that the detection and identification of gamma radiation will occur in completely parallel to the measurement of the neutron flux.

[0042] One big advantage of embodiments of the inventive methods is that they work with a standard RID without a separate neutron detector. It is therefore possible to enable existing RIDs without neutron detection capability by adding such a neutron detection capability without hardware modification. A software update, implementing the disclosed method, may be sufficient.

[0043] At the same time, the inventive method is not limited to those standard RIDs. It may also be used to improve already available neutron detection by combining the measurement results. This is especially true when a scintillator, comprising iodine, is used in combination with a surrounding neutron absorbing material as known in the state of the art, that material capturing neutrons and emitting gamma radiation which is then used to detect the neutron radiation. Any such capture material with a (n, ) reaction, for example .sup.6Li, may be used. Such a neutron absorbing material may also be placed within the crystal itself, which is sometimes the case with .sup.6Li.