Low activity nuclear density gauge

• US RE38,910 E1
• Filed: 09/04/2003
• Issued: 12/06/2005
• Est. Priority Date: 01/10/2002
• Status: Expired due to Term

• Current Assignee: Troxler Electronic Laboratories, Inc.
• Original Assignee: Troxler Electronic Laboratories, Inc.
• Inventors: Dep, W. Linus, Troxler, Robert E.
• Primary Examiner(s): Church, Craig E.
• Application Number:
  US10/654,855
• Time in Patent Office: 824 Days
• Field of Search: 378/86, 378/89
• US Class Current: 378/89
• CPC Class Codes: G01N 23/06 and measuring the absorption

Abstract

A nuclear density gauge and test method is provided for measuring density material in a relatively thin zone beneath a surface of the material. The gauge comprises a gauge housing and a substantially planar base on said gauge housing adapted to be positioned on a surface of the material sample. A gamma radiation source having a characteristic primary energy and an activity of no more than 100 microcurie is mounted within the housing and cooperates with the base for emitting gamma radiation through the base and into an underlying material sample. An energy selective gamma radiation detector is mounted within the gauge housing and in laterally spaced apart relation from the gamma radiation source. The gamma radiation detector is operable for quantifying the energy level of the detected gamma radiation. Shielding is provided within the gauge housing between the source and the detector for preventing gamma radiation from passing directly from said source to the detector. An analyzer is connected to the detector for detecting gamma radiation counts in a predetermined energy spectrum having a lower limit of 0.1 MeV or greater and an upper limit which is less than the characteristic primary energy of said source. The density of the sample is calculated based upon the gamma radiation counts obtained by the analyzer within the predetermined energy spectrum.

Claims

1. A nuclear gauge for measuring the density of a material, said gauge comprising:

a gauge housing having a surface adapted to be positioned on a surface of the material sample;

at least one gamma radiation source within said gauge housing having a characteristic primary energy and having a total activity of no more than 100 microcuries, said at least one source being positioned for emitting gamma radiation through said housing surface and into an underlying material sample;

at least one energy selective gamma radiation detector mounted within the gauge housing in spaced apart relation with respect to said at least one gamma radiation source, said gamma radiation detector being operable for producing signals representing the energy level of detected gamma radiation; and

density calculating means connected to said detector and operable for calculating a value for the density of the material sample based upon detected signals having an energy level within a predetermined portion of the energy spectrum of the gamma radiation detected by said at least one detector.

2. A gauge according to claim 1, wherein said density calculating means includes an analyzer connected to said at least one detector and operable for receiving said signals therefrom, said analyzer including means for classifying and accumulating signals in one or more channels corresponding to said predetermined portion of the energy spectrum.

3. A gauge according to claim 2, wherein said analyzer is a multichannel analyzer for classifying and accumulating signals in a plurality of discrete channels over the energy spectrum of the gamma radiation detected by said at least one detector, and wherein at least one of said discrete channels defines said predetermined portion of the energy spectrum.

4. A gauge according to claim 1, wherein said predetermined portion of the energy spectrum of the gamma radiation has a lower limit of 0.1 MeV and an upper limit which is less than the characteristic primary energy of said source.

5. A gauge according to claim 4, wherein said at least one source comprises at least one Cesium-137 gamma radiation source with a 0.662 MeV primary energy.

6. A gauge according to claim 5, wherein said predetermined energy spectrum falls within the range of from 0.1 MeV to 0.4 MeV.

7. A gauge according to claim 5, wherein said predetermined energy spectrum falls within the range of from 0.1 MeV to 0.25 MeV.

8. A gauge according to claim 1, wherein said at least one gamma radiation source comprises a plurality of point sources, each in spaced apart relation from one another and from said detector.

9. A gauge according to claim 8, wherein said point sources are arranged in a common plane substantially parallel to said base.

10. A gauge according to claim 1 wherein said at least one energy selective gamma radiation detector comprises a sodium iodide crystal and a photomultiplier tube operatively associated with said crystal.

11. A gauge according to claim 1 including an additional gamma radiation source having a characteristic primary energy and an activity of no more than 50 microcurie, said additional source being mounted within said gauge housing and positioned so that gamma radiation can pass directly from said additional source to said detector.

12. A gauge according to claim 1, additionally including background radiation detection means operable for calculating a value representing the ambient background gamma radiation, and wherein said density calculating means cooperates with the background radiation detection means for calculating a value for the density of the material sample which is corrected for ambient background radiation.

13. A gauge according to claim 12, wherein said background radiation detection means includes means to permit placement of said at least one source in a location shielded from said detector so that the detector can detect gamma radiation originating other than from said source.

14. A gauge according to claim 2, additionally including stabilization means associated with said analyzer for correcting for temperature sensitivity of said detector.

15. A gauge according to claim 14, wherein said stabilization means includes means responsive to reference signals in at least one other selected channel of said analyzer, said at least one other selected channel representing an energy level outside of said predetermined portion of the energy spectrum.

16. A gauge according to claim 15, wherein said stabilization means includes an additional gamma radiation source having a characteristic primary energy different from that of said at least one source, and wherein said at least one other selected channel corresponds to the characteristic primary energy of said additional source.

17. A gauge according to claim 1, including a shielded enclosure located within said housing and a disk rotatably mounted within the shielded enclosure, and wherein said gamma radiation source is mounted to said disk, the disk being rotatable to move the source from a retracted shielded position within the shielded enclosure to an exposed position for measurement.

18. A gauge according to claim 1, wherein said density calculating means includes means operable for calculating density values repeatedly during a predetermined counting time, and including a display device cooperating with said density calculating means and operable for displaying the calculated density values as a function of time during said predetermined counting time.

19. A nuclear gauge for measuring the density of a material, said gauge comprising:

a gauge housing;

a base on said gauge housing adapted to be positioned on a surface of the material sample;

at least one gamma radiation source within said gauge housing having a characteristic primary energy and having a total activity of no more than 100 micro curies, said at least one source being positioned for emitting gamma radiation through said base and into an underlying material sample;

at least one energy selective gamma radiation detector mounted within the gauge housing in spaced apart relation with respect to said at least one gamma radiation source, said gamma radiation detector being operable for producing signals representing the energy level of detected gamma radiation;

shielding within said gauge housing and located between said at least one source and said at least one detector for blocking gamma radiation from passing directly from said source to said detector;

an analyzer operatively connected to said detector for receiving said signals therefrom, said analyzer including means for classifying and accumulating signals in one or more channels over the energy spectrum of the detected gamma radiation; and

density calculating means connected to said analyzer and operable for calculating a value for the density of the material sample based upon the accumulated signals in one or more of said channels selected to represent a predetermined portion of the energy spectrum of the gamma radiation detected by said at least one detector.

20. A gauge according to claim 19, wherein both said source and said detector are mounted to said base.

21. A gauge according to claim 20, including a mounting plate upon which said at least one source is located, the mounting plate being detachably connected to a predetermined location on said base to permit removing the source from the gauge housing.

22. A gauge according to claim 21, including a tether connecting the source plate to said base so that it cannot become lost or separated when removed from said base.

23. A gauge according to claim 19, including a shielded enclosure located within said housing and a movable source mount within the shielded enclosure, the source mount allowing movement of the source from a retracted shielded position within the shielded enclosure to an exposed unshielded position for taking measurements.

24. A gauge according to claim 19, wherein said at least one detector comprises a scintillation detector.

25. A gauge according to claim 24, wherein said scintillation detector comprises a sodium iodide crystal and a photomultiplier tube operatively associated with said crystal.

26. A gauge according to claim 19, wherein said detector comprises first and second scintillation detectors positioned within said housing at two geometrically differing source-to-detector relationships.

27. A gauge according to claim 26, including means for adjusting the source-to-detector spacing of at least one of said first and second scintillation detectors.

28. A gauge according to claim 19, including an additional gamma radiation source having a characteristic energy and an activity of no more than 50 microcurie, said additional source being mounted within said gauge housing and positioned so that gamma radiation can pass directly from said additional source to said detector.

29. A gauge according to claim 19, including a channel formed in said shielding for providing a path for gamma radiation to pass directly from said at least one gamma radiation source to said detector.

30. A nuclear gauge for measuring the density of a material, said gauge comprising:

a gauge housing;

a base on said gauge housing adapted to be positioned on a surface of the material sample;

at least one gamma radiation source within said gauge housing having a characteristic primary energy and having a total activity of no more than 100 microcuries, said at least one source being positioned for emitting gamma radiation through said base and into an underlying material sample;

at least one energy selective gamma radiation detector mounted within the gauge housing in spaced apart relation with respect to said at least one gamma radiation source, said gamma radiation detector being operable for producing signals representing the energy level of detected gamma radiation;

shielding within said gauge housing and located between said at least one source and said detector for blocking gamma radiation from passing directly from said source to said detector;

an analyzer operatively connected to said detector for receiving said signals therefrom, said analyzer including means for classifying and accumulating signals in one or more channels over the energy spectrum of the detected gamma radiation;

background radiation detection means connected to said analyzer and operable for calculating a value representing the ambient background gamma radiation,

density calculating means connected to said analyzer and operable for calculating a value for the density of the material sample based upon the accumulated signals in one or more of said channels selected to represent a predetermined portion of the energy spectrum of the gamma radiation detected by said at least one detector, and wherein said density calculating means also cooperates with said background radiation detection means for calculating a value for the density of the material sample which is corrected for ambient background radiation; and

stabilization means associated with said analyzer for correcting for temperature sensitivity of said detector, said stabilization means including means responsive to reference signals in at least one other selected channel of said analyzer, said at least one other selected channel representing an energy level outside of said predetermined portion of the energy spectrum.

31. A gauge according to claim 30, wherein said stabilization means includes an additional gamma radiation source having a characteristic energy different from that of said at least one source and having an activity of no more than 50 microcurie, said additional source being mounted within said gauge housing and positioned so that gamma radiation can pass directly from said additional source to said detector to thereby produce said reference signals, and wherein said means responsive to reference signals is responsive to the characteristic energy level of said additional gamma radiation source.

32. A gauge according to claim 30, wherein said stabilization means includes a channel formed in said shielding for providing a path for gamma radiation to pass directly from said at least one gamma radiation source to said detector to thereby produce said reference signals, and wherein said means responsive to reference signals is responsive to the characteristic energy level of said at least one gamma radiation source.

33. A gauge according to claim 30, including a shielded enclosure located within said housing and a movable source mount within the shielded enclosure, the source mount allowing movement of the source from a retracted shielded position within the shielded enclosure for taking background radiation measurements to an exposed unshielded position for taking density measurements of the material.

34. A nuclear gauge for measuring the density of a material, said gauge comprising:

a gauge housing;

a base on said gauge housing having a lower surface adapted to be positioned on an exposed upper surface of the material sample;

at least one gamma radiation source having a characteristic primary energy and a total activity of no more than 100 microcurie, said at least one source being mounted within said housing and cooperating with said base for emitting gamma radiation through the base and into an underlying material sample;

a sodium iodide crystal gamma radiation detector mounted within the gauge housing and in spaced apart relation from said gamma radiation source,

a photomultiplier tube operably connected to said sodium iodide crystal detector and being operable for generating an electrical signal proportional to the energy of the gamma radiation detected by said sodium iodide detector;

shielding within said gauge housing and located between said source and said detector for shielding gamma radiation from passing directly from said source to said detector;

an analyzer connected to said photomultiplier tube and operable for detecting gamma radiation counts in one or more channels over the energy spectrum of the detected gamma radiation; and

density calculating means connected to said analyzer and operable for calculating a value for the density of the material sample based upon the accumulated signals in one or more of said channels selected to represent a predetermined energy spectrum having a lower limit of 0.1 MeV or greater and an upper limit which is less than the characteristic primary energy of said source.

35. A gauge according to claim 34, wherein said source comprises a ¹³⁷Cs gamma radiation source with a 0.662 MeV primary energy and an activity of no more than 50 microcurie.

36. A gauge according to claim 34, including an additional gamma radiation source having a characteristic primary energy and an activity of no more than 10 microcurie, said additional source being mounted within said gauge housing and positioned so that gamma radiation can pass directly from said additional source to said detector, and wherein said analyzer comprises a digital multichannel analyzer having a spectrum stabilizer utilizing the primary energy peak of said additional source.

37. A gauge according to claim 34 including a bore hole formed in said shielding for providing a path for gamma radiation to pass directly from said source to said detector.

38. A gauge according to claim 34 including a source plate removably mounted to said base, and wherein said gamma radiation source comprises a plurality of discrete sources, each having an activity of no more than 10 microcurie and being mounted to said source plate spaced apart from one another.

39. A gauge according to claim 34 including a shielded enclosure mounted within said housing, and source holder associated with the shielded enclosure and upon which said source is mounted, said source holder being mounted for moving the source between a retracted shielded position located within the shielded enclosure and an exposed operative position where gamma radiation may pass through said base.

40. A method for measuring the density of a material, comprising:

directing gamma radiation into the material from at least one source having a characteristic primary energy and a total activity of no more than 100 microcuries;

detecting gamma radiation which has interacted with and been backscattered by the material and quantifying the energy levels of the detected gamma radiation;

selecting gamma radiation counts having an energy level within a predetermined portion of the energy spectrum of the detected gamma radiation; and

calculating a value for the density of the sample based upon the selected gamma radiation counts within said predetermined portion of the energy spectrum.

41. A method according to claim 40, wherein said step of detecting gamma radiation comprises generating signals representing the energy levels of detected gamma radiation;

and wherein said step of selecting gamma radiation counts comprises classifying and accumulating the signals in one or more channels of an analyzer over the energy spectrum of the detected gamma radiation; and

selecting one or more of the channels representing only a predetermined portion of the energy spectrum of the gamma radiation.

42. A method according to claim 41, wherein said step of selecting one or more channels comprises selecting channels representing gamma radiation with an energy having a lower limit of 0.1 MeV and an upper limit which is less than the characteristic primary energy of said source.

43. A method according to claim 42, wherein the source is Cesium-137 with a 0.662 MeV primary energy, and said step of selecting comprises selecting channels representing gamma radiation with an energy of from 0.1 MeV to 0.4 MeV.

44. A method according to claim 42, additionally including detecting background radiation and correcting the value for the density of the material sample to account for ambient background radiation.

45. A method for measuring the density of a material, comprising:

directing gamma radiation into the material from at least one source having a characteristic primary energy and a total activity of no more than 100 microcurie;

detecting gamma radiation which has interacted with and been backscattered by the material and generating signals representing the energy level of the detected gamma radiation;

classifying the signals according to their energy level and accumulating signal counts in respective channels of an analyzer;

selecting accumulated signals in one or more selected channels of the analyzer representing a predetermined portion of the energy spectrum of the detected gamma radiation; and

calculating a value for the density of the sample based upon the selected accumulated signals; and

,

displaying a calculated density value for the material.

46. A method according to claim 45, wherein said step of classifying and accumulating signals is carried out over a predetermined period of time, and wherein said calculating step and said displaying step are carried out repeatedly during said predetermined period of time.

47. A method according to claim 45, wherein said calculating step includes the step of digitally filtering the signals to decrease the statistical variation in the calculated density values.

48. A nuclear gauge for measuring the density of a material, said gauge comprising:

a gauge housing;

a base gauge housing having a lower surface adapted to be positioned on an underlying surface of the material sample;

at least one gamma radiation source within said gauge housing having a characteristic primary energy, said at least one source being positioned for emitting gamma radiation through said base and into an underlying material sample;

at least one energy selective gamma radiation detector mounted within the gauge housing in spaced apart relation with respect to said at least one gamma radiation source, said gamma radiation detector being operable for producing signals representing the energy level of detected gamma radiation;

shielding within said gauge housing and located between said at least one source and said detector for blocking gamma radiation from passing directly from said source to said detector;

a multichannel analyzer operatively connected to said detector for receiving said signals therefrom, said analyzer including means for classifying and accumulating signals in a plurality of discrete channels, each channel corresponding to a portion of the energy level spectrum of the detected gamma radiation;

density calculating means connected to said analyzer and operable for calculating a value for the density of the material sample based upon the accumulated signals in one or more of said channels selected to represent a predetermined portion of the energy spectrum of the gamma radiation detected by said at least one detector,

stabilization means associated with said analyzer for correcting for temperature sensitivity of said detector, said stabilization means including means responsive to reference signals in at least one other selected channel of said analyzer, said at least one other selected channel representing an energy level outside of said predetermined portion of the energy spectrum.

49. A gauge according to claim 48, wherein said stabilization means includes an additional gamma radiation source having a characteristic primary energy different from that of said at least one source, and wherein said at least one other selected channel corresponds to the characteristic primary energy of said additional source.

50. A gauge according to claim 48, including a shielded enclosure located within said housing and a disk rotatably mounted within the shielded enclosure, and wherein said at least one gamma radiation source is mounted to said disk, the disk being rotatable to move the source from a retracted shielded position within the shielded enclosure to an exposed position for measurement.

51. A gauge according to claim 48, additionally including background radiation detection means connected to said analyzer and operable for calculating a value representing the ambient background gamma radiation, and wherein said density calculating means also cooperates with said background radiation detection means for calculating a value for the density of the material sample which is corrected for ambient background radiation.