Neutron detector

• US 20100019164A1
• Filed: 09/30/2009
• Published: 01/28/2010
• Est. Priority Date: 06/19/2007
• Status: Active Grant

• Current Assignee: Materials Innovation Incorporated
• Original Assignee: Materials Innovation Incorporated
• Inventors: Stephan, Andrew C., Jardret, Vincent D.
• Granted Patent: US 7,919,758 B2
• Time in Patent Office: Days
• US Class Current: 250/390.40
• CPC Class Codes: G01T 3/00 Measuring neutron radiation G01T5/00 takes precedence
• CPC Class Codes: H01J 47/1255 Ionisation chambers

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 having a selected outside surface; and

,

four groups of neutron detecting elements, each group comprising at least one detecting element, each of said groups disposed at a substantially different distance from said selected outside surface so that each of said groups is separated from said selected surface by a substantially different areal density of said moderating material.

2. The apparatus of claim 1 wherein at least two of said four groups of detecting elements may be independently addressable, and each said independently addressable group has a substantially different detection response for neutrons entering said moderating material from said outside surface.

3. The apparatus of claim 1 wherein at least two of said four groups of detecting elements may be addressable with a single detection circuit connected to said two groups of detecting elements in parallel.

4. The apparatus of claim 2 wherein the relative neutron responses of said two groups of detecting elements are correlated to at least one characteristic attribute of said entering neutrons.

5. The apparatus of claim 4 wherein said characteristic attribute of said neutrons comprises an attribute selected from the group consisting of:

neutron energy;

neutron energy spectrum;

neutron directionality;

temporal distribution of neutron detection events;

occurrence of fission chains;

presence of fissile material;

direction to fissile material;

distance to fissile material;

location of fissile material;

shielding of fissile material;

type of fissile material;

amount of fissile material;

isotopic composition of fissile material; and

potential threat level of fissile material.

6. The apparatus of claim 1 wherein said volume of neutron moderating material further comprises a radiation detecting material.

7. The apparatus of claim 6 wherein said radiation detecting material comprises an organic material selected from the group consisting of:

plastic scintillators and liquid scintillators.

8. The apparatus of claim 1 further characterized by the ability, in a substantially monoenergetic fast neutron flux, to detect at least half of said neutrons within 30 μ

s from the time said neutrons enter said moderator volume.

9. An apparatus for detecting fissile materials comprising:

a particle generator configured to provide particles capable of inducing neutron emission from at least one fissile material;

a volume of neutron moderating material having a selected outside surface; and

,

four groups of neutron detecting elements, each group comprising at least one detecting element, each of said groups disposed at a substantially different distance from said selected outside surface so that each of said groups is separated from said selected surface by a substantially different areal density of said moderating material.

10. The apparatus of claim 9 wherein at least two of said four groups of detecting elements may be independently addressable, and each said independently addressable group has a substantially different detection response for neutrons entering said moderating material from said outside surface.

11. The apparatus of claim 9 wherein at least two of said four groups of detecting elements may be addressable with a single detection circuit connected to said two groups of detecting elements in parallel.

12. The apparatus of claim 10 wherein the relative neutron responses of said two groups of detecting elements are correlated to at least one characteristic attribute of said entering neutrons.

13. The apparatus of claim 12 wherein said characteristic attribute of said neutrons comprises an attribute selected from the group consisting of:

neutron energy;

neutron energy spectrum;

neutron directionality;

temporal distribution of neutron detection events;

occurrence of fission chains;

presence of fissile material;

direction to fissile material;

distance to fissile material;

location of fissile material;

shielding of fissile material;

type of fissile material;

amount of fissile material;

isotopic composition of fissile material; and

potential threat level of fissile material.

14. The apparatus of claim 9 wherein said volume of neutron moderating material further comprises a radiation detecting material.

15. The apparatus of claim 14 wherein said radiation detecting material comprises an organic material selected from the group consisting of:

plastic scintillators and liquid scintillators.

16. The apparatus of claim 9 further characterized by the ability, in a substantially monoenergetic fast neutron flux, to detect at least half of said neutrons within 30 μ

s from the time said neutrons enter said moderator volume.

17. An apparatus for detecting neutrons, comprising:

a volume of neutron moderating material having a selected outside surface; and

,

three groups of neutron detecting elements, each group comprising a plurality of individual detecting elements, each of said groups disposed at a substantially different distance from said selected outside surface so that each of said groups is separated from said selected surface by a substantially different areal density of said moderating material.

18. The apparatus of claim 17 wherein at least two of said three groups of detecting elements may be independently addressable, and each said independently addressable group has a substantially different detection response for neutrons entering said moderating material from said outside surface.

19. The apparatus of claim 17 wherein at least two of said three groups of detecting elements may be addressable with a single detection circuit connected to said two groups of detecting elements in parallel.