COMPACT NEUTRON SOURCE AND MODERATOR

• US 20100061500A1
• Filed: 06/11/2007
• Published: 03/11/2010
• Est. Priority Date: 06/09/2006
• Status: Abandoned Application

• Current Assignee: Regents of the University of California (University of California)
• Original Assignee: Regents of the University of California (University of California)
• Inventors: Piestrup, Melvin Arthur, Lou, Tak Pui, Reijonen, Jani
• Application Number:
  US12/303,851
• Publication Number:
  US 20100061500A1
• Time in Patent Office: Days
• US Class Current: 376/114
• CPC Class Codes: A61N 2005/109 Neutrons
• CPC Class Codes: G21G 4/02 Neutron sources
• CPC Class Codes: H05H 3/06 Generating neutron beams targets for producing nuclear reactions H05H6/00; neutron sources G21G4/02
• CPC Class Codes: H05H 6/00 Targets for producing nuclear reactions supports for targets or objects to be irradiated G21K5/08 ; preparation of tritium C01B4/00; targets, e.g. pellets for fusion reactions by laser or charged particles beam injection H05H1/22
• CPC Class Codes: Y02E 30/10 Nuclear fusion reactors

Abstract

A novel method and compact neutron source for generating thermal neutrons is described that uses an ion source to emit ions toward a target where neutrons are generated. Surrounding the target is a secondary electron shield, and surrounding the target is a first stage moderator to reduce the energy of generated fast neutrons. Enclosing the first stage moderator is a second stage moderator with a thermal neutron port.

Claims

1. A neutron source comprising:

an ion source;

a target;

a secondary election shield disposed about said target, said secondary electron shield including an ion entrance aperture disposed to have ions emitted from said ion source impact said target;

a first stage moderator disposed adjacent said secondary electron shield; and

,

a second stage moderator disposed about said first stage moderator.

2. The neutron source according to claim 1 further comprising a plurality of more than one moderator stage disposed about said first stage moderator.

3. The neutron source according to claim 1 with said first stage moderator disposed below said target with said ion source disposed above said target.

4. The neutron source according to claim 1 further comprising a thermal neutron port disposed through said second stage moderator.

5. The neutron source according to claim 4 further comprising a thermal neutron port central axis disposed not to pass through said target where neutrons are generated.

6. The neutron source according to claim 4 further comprising a neutron absorbing material disposed about an exterior surface of said thermal neutron port.

7. The neutron source according to claim 1 further comprising a titanium coating disposed on said target.

8. The neutron source according to claim 1 wherein said first stage moderator includes a layer of water.

9. The neutron source according to claim 1 wherein said second stage moderator includes a layer of polyethylene.

10. The neutron source according to claim 1 wherein said second stage moderator includes a layer of lead loaded polyethylene.

11. The neutron source according to claim 8 wherein said first stage moderator layer of water is at least 3 centimeters thick between said target and a thermal neutron port disposed through a second stage moderator.

12. The neutron source according to claim 10 wherein said second stage moderator layer of lead loaded polyethylene is at least 5 centimeters thick between a first stage moderator disposed about said target and an exterior surface of said second stage moderator.

13. The neutron source according to claim 8 wherein the water is heavy water.

24. The neutron source of claim 1, further comprising:

a tube disposed within the second stage moderator to introduce a sample opposite the target, the sample positioned to receive a flux of thermal neutrons from the target; and

a gamma ray detector located at one or more ends of the tube to detect gamma rays emitted by the sample.

25. The neutron source of claim 24, further comprising a thermal neutron shield substantially enclosing the neutron source, wherein the thermal neutron shield does not cover the one or more tube ends.

26. The neutron source of claim 25, wherein a thickness of the second moderator and a thickness of the thermal neutron shield to increase an amount of thermal neutron flux at the sample while reducing an amount of fast neutrons that may be received at the at least one gamma ray detector.

14. A method of production of neutrons comprising:

directing ions emitted from an ion source to impact a target where neutrons are produced;

capturing secondary electrons at a secondary electron shield disposed about said target;

passing generated neutrons through a first stage moderator disposed about said secondary electron shield or target to provide first moderated neutrons; and

passing the first moderated neutrons thorough a second stage moderator disposed about said first stage moderator.

15. The method according to claim 14 further comprising passing the first moderated neutrons through a thermal neutron port disposed through said second stage moderator.

16. The method according to claim 15 wherein a thermal neutron port central axis is disposed not to pass through said target where neutrons are generated.

17. The method according to claim 15 wherein a neutron absorbing material is coated about an exterior surface of said thermal neutron port.

18. The method according to claim 14 wherein a titanium layer is coated on said target where ions from said ion source impact said target

19. The method according to claim 15 wherein said first stage moderator includes a layer of water.

20. The method according to claim 14 wherein said second stage moderator includes a layer of polyethylene.

21. The method according to claim 14 wherein said second stage moderator includes a layer of lead loaded polyethylene.

22. The method according to claim 17 wherein said first stage moderator layer of water is at least 3 centimeter thick between said target and said thermal neutron port.

23. The method according to claim 21 wherein said second stage moderator layer of lead loaded polyethylene is at least 5 centimeters thick between said first stage moderator and an exterior surface of said second stage moderator.

27. the method of claim 14 further comprising:

providing a tube through the second stage moderator for introducing a sample;

positioning the sample to receive an amount of neutron flux from the target; and

detecting an amount of gamma rays emitted from the sample by a gamma ray detector positioned at one or more ends of the tube.

28. The method of claim 27, further comprising forming a thermal neutron shield to substantially enclose the neutron source, wherein the thermal neutron shield does not cover the one or more tube ends.

29. the method of claim 28, further comprising selecting a thickness of the second moderator and a thickness of the thermal neutron shield to increase an amount of thermal neutron flux at the sample while reducing an amount of last neutrons that may be received at the at least one gamma ray detector.