Composite Gamma-Neutron Detection System

• US 20140042330A1
• Filed: 01/29/2013
• Published: 02/13/2014
• Est. Priority Date: 06/11/2008
• Status: Active Grant

• Current Assignee: Rapiscan Systems Incorporated (OSI Systems Incorporated)
• Original Assignee: Rapiscan Systems Incorporated (OSI Systems Incorporated)
• Inventors: Gozani, Tsahi, Hilliard, Donald Bennett, Bendahan, Joseph, King, Michael Joseph
• Granted Patent: US 8,963,094 B2
• Time in Patent Office: Days
• US Class Current: 250/367
• CPC Class Codes: G01T 1/167 Measuring radioactive content of objects, e.g. contamination whole body counters G01T1/163
• CPC Class Codes: G01T 1/2008 using a combination of different types of scintillation detectors, e.g. phoswich
• CPC Class Codes: G01T 1/203 the detector being made of plastics
• CPC Class Codes: G01T 3/008 using an ionisation chamber filled with a gas, liquid or solid, e.g. frozen liquid, dielectric G01T3/006 takes precedence
• CPC Class Codes: G01T 3/06 with scintillation detectors
• CPC Class Codes: G01V 5/26 Passive interrogation, i.e. by measuring radiation emitted by objects or goods
• CPC Class Codes: G01V 5/281 detecting special nuclear material [SNM], e.g. Uranium-235, Uranium-233 or Plutonium-239
• CPC Class Codes: H01J 43/08 Cathode arrangements construction of photo cathodes H01J40/06, H01J40/16, H01J47/00, H01J49/08
• CPC Class Codes: H01J 43/30 Circuit arrangements not adapted to a particular application of the tube and not otherwise provided for

Abstract

The present invention provides a gamma-neutron detector based on mixtures of thermal neutron absorbers that produce heavy-particle emission following thermal capture. In one configuration, B-10 based detector is used in a parallel electrode plate geometry that integrates neutron moderating sheets, such as polyethylene, on the back of the electrode plates to thermalize the neutrons and then detect them with high efficiency. The moderator can also be replaced with plastic scintillator sheets viewed with a large area photomultiplier tube to detect gamma-rays as well. The detector can be used in several scanning configurations including portal, drive-through, drive-by, handheld and backpack, etc.

Claims

1. A gamma-neutron detector, comprising:

a first layer of neutron sensitive composite scintillator; and

a second and a third layer of gamma sensitive scintillators, wherein the first layer is positioned between the second and third layers.

2. The gamma-neutron detector of claim 1, wherein the first layer comprises one of Li-6, B-10, Cd or Gd mixed with ZnS.

3. The gamma-neutron detector of claim 1, wherein the first layer is formed by vapor drying ZnS or ZnS(Ag) and one of Li-6, B-10, Cd or Gd in a mixture comprising a binder and a solvent.

4. The gamma-neutron detector of claim 2, wherein the Li-6 or B-10 have a density of 20% to 30% by volume with respect to ZnS.

5. The gamma-neutron detector of claim 1, wherein the second and third layers comprise one of an organic solid scintillator, an inorganic solid scintillator, or a liquid scintillator.

6. The gamma-neutron detector of claim 1, wherein the second and third layers comprise plastic scintillators with fast decay time and the first layer comprises scintillators with slower decay time.

7. The gamma-neutron detector of claim 1, wherein the second and third layers are thicker than the first layer.

8. The gamma-neutron detector of claim 7, wherein the thickness of the second and third layers ranges between 0.01 m to 0.20 m.

9. The gamma-neutron detector of claim 1, wherein the second and third layers respectively form front and back panels of different thicknesses.

10. The gamma-neutron detector of claim 1, wherein a plurality of the said gamma sensitive scintillators and a plurality of the said neutron sensitive composite scintillators are placed alternately with each other in a direction substantially perpendicular to the direction of incident radiation.

11. The gamma-neutron detector of claim 1, wherein a plurality of the said gamma sensitive scintillators and a plurality of the said neutron sensitive composite scintillators are placed alternately with each other and are oriented at an angle to the direction of incident radiation.

12. A gamma-neutron detector, comprising:

a gamma detector of plastic scintillator;

a neutron detector having at least one screen comprising a mixture of silver activated ZnS and one of Li-6 or B-10; and

at least one photodetector to collect and convert light produced by the neutron and gamma detectors, respectively, into neutron and gamma events.

13. The gamma-neutron detector of claim 12, further comprising a Pulse-Shape Discriminator to discriminate the neutron and gamma events;

and wherein the at least one screen is embedded within the plastic scintillator.

14. The gamma-neutron detector of claim 12, further comprising a reflector foil positioned between the at least one screen and the plastic scintillator;

and wherein the at least one screen is embedded in a transparent hydrogenous light guide.

15. A detector comprising at least one neutron cell, the said at least one neutron cell comprising:

a first and a second layer comprising B-10 for capturing neutrons; and

a cell layer, comprising gas, positioned between the first and second layers, wherein, when a neutron is captured, the first and second layers emit charged particles that ionize the gas in the cell layer creating free electron and ion pairs.

16. The detector of claim 15, wherein the gas is Argon.

17. The detector of claim 15, wherein the at least one neutron cell further comprises a third and a fourth layer of polyethylene positioned to have the first and the second layer between them.

18. The detector of claim 15, wherein the at least one neutron cell further comprises a third and a fourth layer of gamma sensitive plastic scintillators positioned to have the first and the second layer between them.

19. The detector of claim 15, wherein a plurality of neutron unit cells are stacked together, thereby increasing the efficiency of the composite detector.

20. The detector of claim 15, wherein a plurality of neutron unit cells are tiled together, thereby increasing the area and efficiency of the composite detector.

21. The detector of claim 15, wherein a plurality of neutron unit cells are held together in a foldable geometry.