Claims
- 1. A beta radiation detector comprising:
- an electrically conductive enclosure defining a cavity sufficiently large to allow for interaction to occur between beta radiation and air molecules, said enclosure having an opening at one end for positioning against a surface;
- an electrically conductive signal collector insulatively mounted in said cavity of said electrically conductive enclosure, adjustably spaced inwardly from said opening and defining an indicator for indicating the adjustment position of said electrically conductive signal collector, said electrically conductive signal collector being sized and positioned to substantially span said cavity so that said air ions generated in said cavity through interaction with beta radiation are electrostatically captured by said electrically conductive signal collector and said electrically conductive enclosure when an electric potential is applied between said electrically conductive enclosure and said electrically conductive signal collector, and said electrically conductive signal collector being configured to allow free circulation of air through said cavity and past said electrically conductive signal collector;
- indicator means attached to said electrically conductive signal collector for indicating an electrical current produced by collection of air ions generated in said cavity by beta radiation emanating from said surface; and
- a voltage source connected between said indicator means and said electrically conductive enclosure for creating said electric potential between said electrically conductive enclosure and said electrically conductive signal collector.
- 2. The beta radiation detector as described in claim 1, wherein said electrically conductive signal collector is fixed in position in said electrically conductive enclosure.
- 3. The beta radiation detector as described in claim 2 wherein said beta radiation detector is used to monitor for tritium.
- 4. The beta radiation detector as described in claim 1, wherein said electrically conductive signal collector comprises aluminum.
- 5. The beta radiation detector as described in claim 1, wherein said electrically conductive signal collector comprises copper.
- 6. The beta radiation detector as described in claim 11, wherein said signal collector comprises a perforated sheet of an electrically conductive material.
- 7. The beta radiation detector as described in claim 1, wherein said signal collector comprises a planar electrically conductive grid.
- 8. The beta radiation detector as described in claim 1, wherein said signal collector means comprises an electrode.
- 9. The beta radiation detector as described in claim 1, wherein said signal collector means comprises a copper clad printed circuit board.
- 10. The beta radiation detector as described in claim 1, wherein said voltage source provides a voltage of approximately 300 V.
- 11. The beta radiation detector as described in claim 10, wherein said voltage source comprises a battery.
- 12. The beta radiation detector as described in claim 10, wherein said voltage source comprises a source of alternating current.
- 13. The beta radiation detector as described in claim 10, wherein said electrically conductive enclosure is cylindrically shaped and defines a diameter sized to fit over a top surface of a barrel.
Government Interests
The present invention generally relates to the detection of radiation, and, more specifically, to the detection of beta particle radiation. This invention was made with Government support under Contract No. W-7405-ENG-36 awarded by the U.S. Department of Energy. The Government has certain rights in the invention. For the safety of individuals, the detection of beta particle radiation is of extreme importance in any location where radioactive materials are handled. In the past, the detection of beta radiation from surfaces has been accomplished primarily through two types of monitors. The first involves the use of swipes or smears taken from surfaces to detect loose surface contamination. These samples are analyzed remotely. This technique offers good sensitivity for loose contamination, but is slow, relatively expensive, and dependent on the skill of the individual acquiring the samples. This type of radiation sampling is also subject to missing portions of the contamination. The second technique involves chemical analysis of samples to determine the tritium content of materials. This technique is physically destructive of the sample, and is very slow and expensive.
US Referenced Citations (7)
Number |
Name |
Date |
Kind |
5184019 |
MacArthur et al. |
Feb 1993 |
|
5187370 |
MacArthur et al. |
Feb 1993 |
|
5194737 |
MacArthur et al. |
Mar 1993 |
|
5281824 |
MacArthur et al. |
Jan 1994 |
|
5298754 |
Anderson et al. |
Mar 1994 |
|
5311025 |
MacArthur et al. |
May 1994 |
|
5539208 |
Overhoff |
Jul 1996 |
|
Foreign Referenced Citations (1)
Number |
Date |
Country |
6-96720 |
Apr 1994 |
JPX |