Neutron detector

• US 7,514,694 B2
• Filed: 06/19/2007
• Issued: 04/07/2009
• Est. Priority Date: 06/19/2007
• Status: Expired due to Fees

• Current Assignee: Materials Innovation Incorporated
• Original Assignee: Materials Innovation Incorporated
• Inventors: Stephan, Andrew C., Jardret, Vincent D.
• Primary Examiner(s): Hannaher; Constantine
• Application Number:
  US11/820,346
• Publication Number:
  US 20080315109A1
• Time in Patent Office: 658 Days
• Field of Search: 250/390.01, 250/390.02, 250/390.03, 250/390.04, 250/390.05, 250/390.06, 250/390.07, 250/390.08, 250/390.09, 250/390.1, 250/390.11, 250/390.12
• US Class Current: 250/390.01
• CPC Class Codes: G01T 3/00 Measuring neutron radiation G01T5/00 takes precedence

Abstract

A neutron detector has a volume of neutron moderating material and a plurality of individual neutron sensing elements dispersed at selected locations throughout the moderator, and particularly arranged so that some of the detecting elements are closer to the surface of the moderator assembly and others are more deeply embedded. The arrangement captures some thermalized neutrons that might otherwise be scattered away from a single, centrally located detector element. Different geometrical arrangements may be used while preserving its fundamental characteristics. Different types of neutron sensing elements may be used, which may operate on any of a number of physical principles to perform the function of sensing a neutron, either by a capture or a scattering reaction, and converting that reaction to a detectable signal. High detection efficiency, an ability to acquire spectral information, and directional sensitivity may be obtained.

Claims

1. An apparatus for detecting neutrons comprising:

a volume of neutron moderating material; and

two pairs of independently readable neutron detecting elements disposed within said moderator volume, the first of said pairs being equidistant from a selected outside surface of said moderator and separated from said selected outside surface of said moderator by no more than 2 g/cm² areal density of said moderating material, and the second of said pairs being equidistant from a selected outside surface of said moderator and separated from said selected outside surface of said moderator by a greater density of moderating material than separates said first pair from said first selected surface.

2. The apparatus of claim 1 wherein said neutron moderating material comprises a material selected from the group consisting of:

water, heavy water, granular inorganic materials, graphite, concrete, polymers, and polymer composites.

3. The apparatus of claim 2 wherein said moderating material comprises a material containing at least 5% atom density of an element selected from the group consisting of:

H, Be, B, C, and N.

4. The apparatus of claim 1 wherein at least some of said neutron detecting elements comprise gas filled hollow dielectric capsules.

5. The apparatus of claim 4 wherein said neutron detecting elements further comprise:

electrodes disposed in electrical contact with opposite sides of said hollow dielectric capsules whereby an electrical pulse may be collected in response to the passage of said neutron; and

,

a detecting circuit connected to said electrodes.

6. The apparatus of claim 1 wherein said moderator comprises a geometrical shape selected from the group consisting of:

rectangular prisms, spheres, and cylinders.

7. An apparatus for detecting neutrons comprising:

a volume of neutron moderating material; and

,

at least four independently readable neutron detecting elements disposed within said moderator volume, said four elements arranged to form three individually addressable pairs defining three non-parallel directions,

wherein each of said three pairs is characterized by the property that each of the two respective detecting elements forming said pair return substantially equivalent neutron detection results when the apparatus is exposed to a neutron flux coming from one direction and said two detecting elements return substantially different neutron detection results when a neutron flux is applied from another direction.

8. The apparatus of claim 7 wherein said three nonparallel directions comprise three axes of a cartesian coordinate system.

9. The apparatus of claim 7 wherein said neutron moderating material comprises a material selected from the group consisting of:

water, heavy water, granular inorganic materials, graphite, concrete, polymers, and polymer composites.

10. The apparatus of claim 7 wherein at least some of said neutron detecting elements comprise gas filled hollow dielectric capsules.

11. The apparatus of claim 10 wherein said neutron detecting elements further comprise:

electrodes disposed in electrical contact with opposite sides of said hollow dielectric capsules whereby an electrical pulse may be collected in response to the passage of said neutron; and

,

a detecting circuit connected to said electrodes.

12. The apparatus of claim 7 wherein said moderator comprises a geometrical shape selected from the group consisting of:

rectangular prisms, spheres, and cylinders.

13. A method for detecting neutrons comprising the steps of:

forming a volume of neutron moderating material having a selected size and shape; and

,

measuring the thermal neutron flux in at least two pairs of locations within said volume, the first of said pairs being equidistant from a selected outside surface of said moderator and separated from said surface of said moderator by no more than 2 g/cm² areal density of said moderating material, and the second of said pairs being equidistant from a selected outside surface of said moderator and separated from said outside surface of said moderator by a greater density of moderating material than separates said first pair from said outside surface.

14. The method of claim 13 further comprising the step of:

comparing the neutron fluxes measured at said two pairs of locations within said moderator to determine at least one characteristic attribute of said neutrons.

15. The method of claim 14 wherein said characteristic attribute of said neutrons comprises an attribute selected from the following group:

neutron energy, neutron energy spectrum, general direction from which neutrons are being emitted, presence of a thermal neutron source, presence of a fast neutron source, presence of a source emmitting both fast and thermal neutrons, presence of a shielded neutron source, presence of fissile material, and isotopic composition of a neutron source.