Device and method for detecting neutrons and gamma rays
View Patent ↗A device for detecting neutrons and gamma rays comprises at least one detector and an acquisition and data-analysis system, connected to the detector; the detector comprises an active part that is formed by a plurality of: scintillator layers, made of a scintillator material, in particular a plastic scintillator; and absorber layers, containing at least one neutron-absorbing material, in particular cadmium or gadolinium; the acquisition and data-analysis system is configured so as to: analyze the signals coming from the detector and calculate the total energy released within the detector following upon an interaction with gamma rays or neutrons; and discriminate between gamma rays and neutrons impinging upon the detector according to whether the energy detected is higher or lower than a pre-set threshold.
1. A device ( 1 ) for detecting neutrons and gamma rays, coming from radionuclides carried by persons and/or vehicles moving along a pre-set path, comprising at least one detector ( 2 ) and an acquisition and data-analysis system ( 3 ) connected to the detector ( 2 ); wherein the detector ( 2 ) has just one active part ( 7 ) that extends along a longitudinal axis (A) and only includes one or more active materials sensitive to gamma rays, being formed by: a plurality of scintillator layers ( 8 ) sensitive to gamma rays, made of a scintillator material sensitive to gamma rays; and, set in between, absorber layers ( 9 ), containing at least one neutron-absorbing material; the scintillator layers ( 8 ) and the absorber layers ( 9 ) having substantially the shape of a thin sheet or plate and being coupled to one another on respective substantially plane faces; and wherein both the gamma rays and the neutrons are detected via the same scintillator layers ( 8 ) sensitive to the gamma rays and via the gamma emission generated by interaction of the neutrons with the absorber material of the absorber layers ( 9 ); the device ( 1 ) being characterized in that the detector ( 2 ) is organized in sections, the scintillator layers ( 8 ) and the absorber layers ( 9 ) being arranged in two or more active sections ( 15 A, 15 B) formed by respective groups of scintillator layers ( 8 ) alternating with absorber layers ( 9 ); each active section ( 15 A, 15 B) having two or more scintillator layers ( 8 ), which alternate with absorber layers ( 9 ) and are optically connected to a single pair of photomultipliers ( 13 A, 13 B), set at respective axially opposite longitudinal ends ( 11 A, 11 B) of the active section ( 15 A, 15 B) for collecting energy released by the interaction of the gamma rays with the scintillator material, each pair of photomultipliers ( 13 A, 13 B) being optically connected to a number of scintillator layers ( 8 ) alternating with absorber layers ( 9 ), and the active sections ( 15 A, 15 B) being read independently by the respective photomultipliers ( 13 A, 13 B), said active sections being asymmetrical with respect to a longitudinal plane, parallel to the axis (A), to the scintillator layers ( 8 ), and to the absorber layers ( 9 ) of the device; said active sections having a different thickness and/or a different number of scintillator layers ( 8 ) alternating with absorber layers ( 9 ).
2. The device according to claim 1 , wherein the first active section ( 15 A), which is set in the front part of the device ( 1 ) and faces in use an object/source to be monitored, has a thickness and/or a number of scintillator layers ( 8 ) alternating with absorber layers ( 9 ) smaller than the second active section ( 15 B), which is set in the rear part of the device ( 1 ) and faces in use the side opposite to the object/source to be monitored.
3. The device according to claim 1 , wherein the scintillator material is a polyvinyltoluene plastic scintillator; and the neutron absorbing material is cadmium or gadolinium.
4. The device according to claim 1 , wherein each absorber layer ( 9 ) that separates two scintillator layers ( 8 ) contains a total amount of absorber material comprised between approximately 2 mg/cm 2 and approximately 2 g/cm 2 .
5. The device according to claim 1 , wherein the optical coupling between the photomultipliers ( 13 ) and the respective active sections ( 15 A, 15 B) is either obtained by direct contact or via light guides ( 14 ) that connect the photomultipliers ( 13 ) to the respective active sections ( 15 A, 15 B).
6. The device according to claim 1 , wherein the photomultipliers ( 13 ) are connected to the respective active sections ( 15 A, 15 B) by respective light guides ( 14 ); each light guide ( 14 ) having an entry ( 17 ), joined to an edge ( 16 ) of an end ( 11 ) of the respective active section ( 15 A, 15 B) and having the shape of said edge ( 16 ), substantially rectangular; and an outlet ( 18 ), opposite to the entry ( 17 ) and joined to a photomultiplier ( 13 ) and basically having the shape of an entry section of the photomultiplier ( 13 ) to which it is joined.
7. The device according to claim 1 , wherein the two active sections ( 15 A, 15 B) are separated by a plate ( 20 ) containing a greater amount of absorber material than each of the absorber layers ( 9 ).
8. The device according to claim 1 , wherein the device ( 1 ) has a portal configuration and constitutes a portal ( 5 ) for monitoring the radiation for detecting radionuclides possibly carried by persons and/or vehicles moving through the portal ( 5 ); the device ( 1 ) comprising a pair of facing detectors ( 2 ) connected to the acquisition and data-analysis system ( 3 ).
9. The device according to claim 8 , wherein each detector ( 2 ) is constituted by one or more modular functional units ( 6 ), that can be combined together and are set alongside one another horizontally and/or set on top of one another vertically, to constitute portals ( 5 ) of different size and/or capacity.
10. The device according to claim 1 , wherein the acquisition and data-analysis system ( 3 ) is configured so as to: analyse the signals coming from the detector ( 2 ) and calculate the total energy released within the detector ( 2 ) following upon an interaction with gamma rays or neutrons; and discriminate between gamma rays and neutrons incident on the detector ( 2 ) according to whether the energy is higher or lower than a pre-set threshold.
11. The device according to claim 10 , wherein the acquisition and data-analysis system ( 3 ) is configured so as to: calculate the total energy E TOT of an event released within the scintillator layers ( 8 ) and compare said total energy E TOT with a pre-set limit value E LIM ; and classify the event as:
an event originating from a gamma source, if E TOT <E LIM ; and
an event originating from a neutron source, if E TOT ≥E LIM .
12. The device according to claim 11 , wherein the acquisition and data-analysis system ( 3 ) is configured so as to: calculate the total energy E TOT of the event as sum of the energies E FRONT , E BACK released within the scintillator layers ( 8 ) of the first active section ( 15 A) and of the second active section ( 15 B), respectively; and classify the event as originating from a neutron source only in the presence of a non-zero signal in the active section ( 15 B) set furthest away in use from the object/source to be monitored, i.e., if E TOT ≥E LIM and E BACK >0.
13. The device according to claim 11 , wherein the acquisition and data-analysis system ( 3 ) is configured so as to classify the event, in the case of events classified as originating from a gamma source, in energy sub-intervals for basic identification of the source.
14. A method for detecting neutrons and gamma rays emitted by radionuclides, comprising the steps of:
providing a device ( 1 ) for detecting neutrons and gamma rays according to claim 3 ;
analysing the signals coming from the detector ( 2 ) of the device ( 1 ) and calculating the total energy released within the detector ( 2 ) following upon an interaction with gamma rays or neutrons; and
discriminating between gamma rays and neutrons incident on the detector ( 2 ) according to whether said energy is higher or lower than a pre-set threshold.
15. The method according to claim 14 , comprising the steps of: calculating the total energy E TOT of an event released within the scintillator layers ( 8 ) and comparing said total energy E TOT with a pre-set limit value E LIM ; and classifying the event as:
an event originating from a gamma source, if E TOT <E LIM ; and
an event originating from a neutron source, if E TOT ≥E LIM .
16. The method according to claim 15 , wherein: the total energy E TOT of the event is computed as sum of the energies E FRONT , E BACK released within the scintillator layers ( 8 ) of the first active section ( 15 A) and of the second active section ( 15 B), respectively; and the event is classified as originating from a neutron source only in the presence of a non-zero signal in the active section ( 15 B) set furthest away in use from the object/source to be monitored, i.e., if E TOT ≥E LIM and E BACK >0.
17. The method according to claim 15 , comprising the steps of classifying the event, in the case of events classified as originating from a gamma source, in energy sub-intervals for basic identification of the source.
18. The device of claim 3 wherein said plastic scintillator is formed of polyvinyltoluene.
19. The method of claim 14 wherein said plastic scintillator of said device is formed of polyvinyltoluene.