Patent Number: 
Section: claims

1. A method of detecting a presence of a material comprising an actinide in a container, comprising:a) locating the container such that at least one neutron detector capable of distinguishing between photons and neutrons is positioned to view the said container at a first viewing angle relative to a photon beam;b) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than a first predetermined cutoff photon energy;c) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;d) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron; ande) based upon the determined energy of a statistically significant number of said detected energetic prompt neutrons exceeding a predetermined value, identifying the material comprising the actinide as present in the container. 2. The method of claim 1, wherein the predetermined value is a difference between the first predetermined cutoff photon energy and a lower energy. 3. The method of claim 2, wherein the lower energy is a threshold energy for production of neutrons by a (γ, n) process in a specified material. 4. The method of claim 2, wherein the lower energy is no greater than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 5. The method of claim 2, wherein the lower energy is a predetermined amount less than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 6. The method of claim 2, wherein the lower energy is determined based upon materials potentially present in the container. 7. The method of claim 2, wherein the lower energy is determined based upon materials present in the container. 8. The method of claim 1, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a bremsstrahlung beam produced by electrons of the first predetermined cutoff energy. 9. The method of claim 1, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a monochromatic photon beam. 10. The method of claim 1, wherein determining the energy of the said detected neutron comprises measuring a time of flight of the said detected neutron. 11. The method of claim 1, wherein determining the energy of the said detected neutron comprises analyzing an energy deposited in at least one of said at least one neutron detector. 12. The method of claim 1, wherein the container is located such that at least two neutron detectors capable of distinguishing between photons and neutrons view the said container, the said neutron detectors viewing the container from different viewing angles relative to the photon beam, and neutrons are detected in at least two of said at least two neutron detectors; further comprisingf) determining a total neutron yield in at least two of said at least two neutron detectors in a predetermined neutron energy range; andg) based upon comparing the said total neutron yields from the said at least two neutron detectors viewing the container from different viewing angles relative to the photon beam, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 13. The method of claim 1, further comprising:f) for at least one new viewing angle different from said first viewing angle relative to the photon beam,i) moving at least one of said at least one neutron detector such that at least one of said at least one moved neutron detector views the said container from the said new viewing angle relative to the photon beam;ii) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;iii) detecting in at least one of said at least one moved neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container; andiv) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;g) for at least two of said first and said at least one new viewing angles relative to the photon beam, determining a total neutron yield in at least one of said at least one neutron detector and at least one o east one moved neutron detector in a predetermined neutron energy range at the said viewing angle relative to the photon beam; andh) based upon comparing the said total neutron yields, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 14. The method of claim 1, wherein the container is located such that at least two neutron detectors capable of distinguishing between photons and neutrons view the said container, at least two of the said at least two detectors viewing the container from different viewing angles relative to the photon beam, and neutrons are detected in at least two of said at least two neutron detectors; further comprising:f) determining a neutron energy distribution in at least two of said at least two neutron detectors; andg) based upon comparing the said neutron energy distributions from the said at least two neutron detectors viewing the container from different viewing angles relative to the photon beam, determining that the present actinide is an odd-even isotope if the energy distributions do not change by more than a predetermined amount as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the energy distributions change by more than a predetermined amount as a function of angle relative to the photon beam. 15. The method of claim 1, further comprising:f) for at least one new viewing angle different from said first viewing angle relative to the photon beam,i) moving at least one of said neutron detectors such that the said moved neutron detector views the said container from the said new viewing angle relative to the photon beam;ii) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;iii) detecting in said at least one moved neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container; andiv) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;g) for at least two of said first and said at least one new viewing angles relative to the photon beam, determining a neutron energy distribution in at least one of said at least one neutron detector and at least one of said at least one moved neutron detector in a predetermined neutron energy range at the said viewing angle relative to the photon beam; andh) based upon comparing the said neutron energy distributions, determining that the present actinide is an odd-even isotope if the energy distributions do not change by more than a predetermined amount as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the energy distributions change by more than a predetermined amount as a function of angle relative to the photon beam. 16. The method of claim 1, further comprising:f) illuminating at least a portion of the said container with at least one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at east one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;i) choosing a higher neutron energy region where neutrons from a (γ, n) process are not energetically permitted for any of said predetermined cutoff photon energies, and a lower energy region where neutrons from a (γ, n) process are energetically permitted for all of said predetermined cutoff photon energies;j) for each said predetermined cutoff photon energy, determining a neutron yield in at least one of said at least one neutron detector in at least two predetermined neutron energy ranges, wherein at least one predetermined neutron energy range encompasses the higher energy region where neutrons from a (γ, n) process are not energetically permitted; and wherein at least one other predetermined neutron energy range encompasses the lower energy region where neutrons from a (γ, n) process are energetically permitted; andk) based upon comparing the said determined neutron yields in at least one of said at least one neutron detector, resulting respectively from said photon beam and said at least one additional photon beam comprising photons of energies no greater than said first and new different predetermined cutoff energies, respectively, confirming that the material comprising the present actinide is present in the container if an increase in the said neutron yield between a lower predetermined cutoff photon energy and a higher predetermined cutoff photon energy, in the higher predetermined neutron energy range where neutrons from a (γ, n) process are not energetically permitted, is not substantial in comparison to an increase in neutron yield in the lower predetermined neutron energy range, where neutrons from a (γ, n) process are energetically permitted. 17. The method of claim 1, further comprising:f) illuminating at least a portion of the said container with at least one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;i) for at least two of said predetermined cutoff photon energies, determining a neutron energy distribution in at least one of said at least one neutron detector; andj) based upon comparing the said determined neutron energy distributions in at least one of said at least one neutron detector, resulting respectively from said photon beam and said at least one additional photon beam comprising photons of energies no greater than said first and new different predetermined cutoff energies, respectively, confirming that the material comprising the present actinide is present in the container if the said neutron energy distributions change by no more than a predetermined amount as a function of cutoff photon energy. 18. The method of claim 1, further comprising:f) illuminating at least a portion of the said container with at east one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at east one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;i) for each said predetermined cutoff photon energy, determining a neutron yield in at least one of said at least one neutron detector in a plurality of predetermined neutron energy ranges;j) for each said predetermined neutron energy range; determining a neutron yield curve as a function of photon cutoff energy; andk) based upon comparing the said determined neutron yield curves in at least one of said at least one neutron detector for the said predetermined neutron energy ranges, confirming that the material comprising the present actinide is present in the container if the said neutron yield curves change by no more than a predetermined amount as a function of neutron energy. 19. A method of detecting a presence of a material comprising an actinide in a container, comprising:a) locating the container such that at least one neutron detector capable of distinguishing between photons and neutrons is positioned to view the said container at a first viewing angle relative to a photon beam;b) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than a first predetermined cutoff photon energy;c) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;d) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron; ande) based upon the determined minimum energy of a statistically significant number of said detected energetic prompt neutrons exceeding a predetermined value, identifying the material comprising the actinide as present in the container. 20. The method of claim 19, wherein the predetermined value is a difference between the first predetermined cutoff photon energy and a lower energy. 21. The method of claim 20, wherein the lower energy is a threshold energy for production of neutrons by a (γ, n) process in a specified material. 22. The method of claim 20, wherein the lower energy is no greater than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 23. The method of claim 20, wherein the lower energy is a predetermined amount less than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 24. The method of claim 20, wherein the lower energy is determined based upon materials potentially present in the container. 25. The method of claim 20, wherein the lower energy is determined based upon materials present in the container. 26. The method of claim 19, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a bremsstrahlung beam produced by electrons of the first predetermined cutoff energy. 27. The method of claim 19, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a monochromatic photon beam. 28. The method of claim 19, wherein determining the minimum energy of the said detected neutron comprises analyzing an energy deposited in at least one of said at least one neutron detector. 29. The method of claim 19, wherein the container is located such that at least two neutron detectors capable of distinguishing between photons and neutrons view the said container, the said neutron detectors viewing the container from different viewing angles relative to the photon beam, and neutrons are detected in at least two of said at least two neutron detectors; further comprisingf) determining a total neutron yield in at least two of said at least two neutron detectors in a predetermined neutron minimum energy range; andg) based upon comparing the said total neutron yields from the said at least two neutron detectors viewing the container from different viewing angles relative to the photon beam, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 30. The method of claim 19, further comprising:f) for at least one new viewing angle different from said first viewing angle relative to the photon beam,i) moving at least one of said at least one neutron detector such that at least one of said moved at least one neutron detector views the said container from the said new viewing angle relative to the photon beam;ii) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;iii) detecting in at least one of said at least one moved neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container; andiv) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron;g) for at least two of said first and said at least one new viewing angle relative to the photon beam, determining a total neutron yield in at least one of said at least one neutron detector and at least one of said at least one moved neutron detector in a predetermined neutron minimum energy range at the said viewing angle relative to the photon beam; andh) based upon comparing the said total neutron yields, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 31. The method of claim 19, wherein the container is located such that at least two neutron detectors capable of distinguishing between photons and neutrons view the said container, at least two of the said at least two detectors viewing the container from different viewing angles relative to the photon beam, and neutrons are detected in at least two of said at least two neutron detectors; further comprising:f) determining a neutron minimum energy distribution in at least two of said at least two neutron detectors; andg) based upon comparing the said neutron minimum energy distributions from the said at least two neutron detectors viewing the container front different viewing angles relative to the photon beam, determining that the present actinide is an odd-even isotope if the minimum energy distributions do not change by more than a predetermined amount as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the minimum energy distributions change by more than a predetermined amount as a function of angle relative to the photon beam. 32. The method of claim 19, further comprising:f) for at least one new viewing angle different from said first viewing angle relative to the photon beam,i) moving at least one of said neutron detectors such that the said moved neutron detector views the said container from the said new viewing angle relative to the photon beam;ii) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;iii) detecting in said at least one moved neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container; andiv) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron;g) for at least two of said first and said at least one new viewing angles relative to the photon beam, determining a neutron minimum energy distribution in at least one of said at least one neutron detector and at least one of said at least one moved neutron detector in a predetermined neutron minimum energy range at the said viewing angle relative to the photon beam; andh) based upon comparing the said neutron minimum energy distributions determining that the present actinide is an odd-even isotope if the minimum energy distributions do not change by more than a predetermined amount as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the minimum energy distributions change by more than a predetermined amount as a function of angle relative to the photon beam. 33. The method of claim 19, further comprising:f) illuminating at least a portion of the said container with at least one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron;i) choosing a higher neutron energy region where neutrons from a (γ, n) process are not energetically permitted for any of said predetermined cutoff photon energies, and a lower energy region where neutrons from a (γ, n) process are energetically permitted for all of said predetermined cutoff photon energies;j) for each said predetermined cutoff photon energy, determining a neutron yield in at least one of said at least one neutron detector in at least two predetermined neutron minimum energy ranges, wherein at least one predetermined neutron minimum energy range encompasses the higher energy region where neutrons from a (γ, n) process are not energetically permitted; and wherein at least one other predetermined neutron minimum energy range encompasses the lower energy region where neutrons from a (γ, n) process are energetically permitted; andk) based upon comparing the said determined neutron yields in at least one of said at least one neutron detector, resulting respectively from said photon beams and said at least one additional photon beam comprising photons of energies no greater than said first and new different predetermined cutoff energies, respectively, confirming that the material comprising the present actinide is present in the container if an increase in the said neutron yield between a lower predetermined cutoff photon energy and a higher predetermined cutoff photon energy, in the higher predetermined neutron minimum energy range where neutrons from a (γ, n) process are not energetically permitted, is not substantial in comparison to an increase in neutron yield in the lower predetermined neutron minimum energy range, where neutrons from a (γ, n process are energetically permitted. 34. The method of claim 19, further comprising:f) illuminating at least a portion of the said container with at least one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron;i) for at least two of said predetermined cutoff photon energies, determining a neutron minimum energy distribution in at least one of said at least one neutron detector; andj) based upon comparing the said determined neutron minimum energy distributions in at least one of said at least one neutron detector, resulting respectively from said photon beams and said at least one additional photon beam comprising photons of energies no greater than said first and new different predetermined cutoff energies, respectively, confirming that the material comprising the present actinide is present in the container if the said neutron minimum energy distributions change by no more than a predetermined amount as a function of cutoff photon energy. 35. The method of claim 19, further comprising:f) illuminating at least a portion of the said container with at least one additional photon beam each having a new different predetermined cutoff photon energy, each new different predetermined cutoff photon energy also being different from said first predetermined cutoff energy such as to comprise only photons of energies no greater than said new different predetermined cutoff energy;g) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of at least one of said at least one additional photon beam with at least a portion of the said container;h) for each of a plurality of said detected energetic prompt neutrons, determining a minimum energy of the said detected neutron;i) for each said predetermined cutoff photon energy, determining a neutron yield in at least one of said at least one neutron detector in a plurality of predetermined neutron minimum energy ranges;j) for each said predetermined neutron minimum energy range; determining a neutron yield curve as a function of photon cutoff energy; andk) based upon comparing the said determined neutron yield curves in at least one of said at least one neutron detector for the said predetermined neutron minimum energy ranges, confirming that the material comprising the present actinide is present in the container if the said neutron yield curves change by no more than a predetermined amount as a function of neutron energy. 36. A method of detecting a presence of a material comprising an actinide in a container, comprising:a) locating the container such that at least one neutron detector capable of distinguishing between photons and neutrons is positioned to view the said container at a first viewing angle relative to a photon beam;b) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than a first predetermined cutoff photon energy;c) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;d) determining that an energy of a statistically significant number of said detected energetic prompt neutrons exceeds a predetermined value; ande) based upon the determination that the energy of the statistically significant number of said detected energetic prompt neutrons exceeds the predetermined value, identifying the material comprising the actinide as present in the container. 37. The method of claim 36, wherein the predetermined value is a difference between the first predetermined cutoff photon energy and a lower energy. 38. The method of claim 37, wherein the lower energy is a threshold energy for production of neutrons by a (γ, n) process in a specified material. 39. The method of claim 37, wherein the lower energy is no greater than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 40. The method of claim 37, wherein the lower energy is a predetermined amount less than a threshold energy for production of neutrons by a (γ, n) process in a specified material. 41. The method of claim 37, wherein the lower energy is determined based upon materials potentially present in the container. 42. The method of claim 37, wherein the lower energy is determined based upon materials present in the container. 43. The method of claim 36, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a bremsstrahlung beam produced by electrons of the first predetermined cutoff energy. 44. The method of claim 36, wherein the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy is a monochromatic photon beam. 45. The method of claim 36, wherein determining that the energy of the statistically significant number of said detected energetic prompt neutrons exceeds a predetermined value comprises analyzing an energy deposited in at least one of said at least one neutron detector. 46. The method of claim 36, wherein the container is located such that at least two neutron detectors capable of distinguishing between photons and neutrons view the said container, the said neutron detectors viewing the container from different viewing angles relative to the photon beam, and neutrons are detected in at least two of said at least two neutron detectors; further comprisingf) determining a total neutron yield in at least two of said at least two neutron detectors in a predetermined neutron energy range; andg) based upon comparing the said total neutron yields from the said at least two neutron detectors viewing the container from different viewing angles relative to the photon beam, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 47. The method of claim 36, further comprising:f) for at least one new viewing angle different from said first viewing angle relative to the photon beam,i) moving at least one of said at least one neutron detector such that at least one of said at least one moved neutron detector views the said container from the said new viewing angle relative to the photon beam;ii) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;iii) detecting in at least one of said at least one moved neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container; andiv) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron;g) for at least two of said first and said at least one new viewing angles relative to the photon beam, determining a total neutron yield in at least one of said at least one neutron detector and at least one of said at least one moved neutron detector in a predetermined neutron energy range at the said viewing angle relative to the photon beam; andh) based upon comparing the said total neutron yields, determining that the present actinide is an odd-even isotope if the total yields disclose an isotropic distribution of neutrons as a function of angle relative to the photon beam, and determining that the present actinide is an even-even isotope if the total yields disclose an anisotropic distribution of neutrons as a function of angle relative to the photon beam. 48. A method of detecting a presence of a material comprising an actinide in a container, comprising:a) locating the container such that at least one neutron detector capable of distinguishing between photons and neutrons is positioned to view the said container at a first viewing angle relative to a photon beam;b) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than a first predetermined cutoff photon energy;c) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;d) determining that more than a predetermined number of energetic prompt neutrons with energies above a first predetermined value have been detected;e) selecting a second predetermined value of energy greater than said first predetermined value;f) illuminating at least a portion of the said container with a photon beam comprising photons of energies no greater than the first predetermined cutoff photon energy;g) detecting in at least one of said at least one neutron detector some additional energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;h) based upon a determined energy of a statistically significant number of said additional energetic prompt neutrons exceeding the second predetermined value, identifying the material comprising the actinide as present in the container.