The present invention is directed to improved methods and apparatus capable of determining elapsed time intervals, and, in particular, to improved methods and apparatus enabling highly accurate determinations of elapsed time intervals that are clearly displayed without consuming power and may be used for warranty, maintenance, and other purposes.
Warranty verification is an extremely important aspect of modern commerce. In this regard, the ability to detect product substitution, tampering, theft, and other problems leading to violations of warranties is increasingly important. Furthermore, it is important for general maintenance of equipment, such as electronic equipment, to more easily know when a part or product is nearing a periodic maintenance term, whereby it is to be evaluated and possibly exchanged.
Many approaches exist for indicating elapsed time intervals for use with products. A significant number of approaches use electronic time measuring devices and/or electronic displays of elapsed time. For example, in the nuclear field, dosimeters are used with electronic timers to measure the amount of radiation over a period of time that might be indicative of dangerous radiation levels. Other efforts to measure time include utilizing color-changing materials. For example, there are known materials that change color, but are highly sensitive to thermal variations. Hence, they are not as reliable as might otherwise be desired for a variety of commercial and industrial applications. Therefore, continuing efforts are being undertaken in this field, especially in terms of improving the accuracy of elapsed time determinations in a non-power consuming manner that displays clearly the results of elapsed time, and is low-cost, safe, highly versatile, and reliable.
Without continued improvements in methods and apparatus enabling highly accurate determinations of elapsed time intervals in a non-power consuming manner whereby results of elapsed time are displayed clearly, and which is low-cost, safe, highly versatile, and reliable, the true potential of improved warranty verification and maintenance management for products and parts may not be fully achieved.
The present invention provides without negative effect and in a manner that overcomes disadvantages of the prior art, enhanced methods and apparatus enabling determinations of elapsed time intervals in a non-power consuming manner, whereby the results of elapsed time are displayed clearly, and in a low-cost, safe, highly versatile, and reliable manner.
One aspect of an illustrated embodiment is a method and apparatus enabling the definition of a time interval, comprising: providing a source of ionizing radiation having at least a first surface that radiates emissions thereof; placing a first surface of a radiation sensitive display material responsive to ionizing radiation in a close proximity relationship to the first surface of the source of ionizing radiation so that the radiated emissions of the source strike the radiation sensitive display material, whereby a time interval is commenced; and, measuring changes in characteristics of the radiation sensitive display material that are indicative of the elapsed time that the radiated emissions of the source strike and effect changes in the radiation sensitive display material after being placed in the close proximity relationship.
Another aspect of an illustrated embodiment is a method and apparatus defining a time interval, comprising: providing a source of radiation that radiates emissions; measuring a first reading at an initial time, of the radiation level of the radiated emissions; placing a radiation suppression element in overlying relationship to the source of radiation so that the radiated emissions are suppressed from passing through the radiation suppression element; removing the radiation suppression element from the overlying relationship; and, measuring a second reading at a later time, of the radiation level of the radiated emissions of the source of radiation, whereby differences in measured levels of radiation between the first and second readings are indicative of elapsed time between the first and second readings.
Yet another aspect of the present embodiments is providing a method and apparatus that yields a high degree of specificity and high reliability in terms of measuring time intervals and which is directly readable without consuming electric power.
Yet still another aspect of the present embodiments is providing a method and apparatus that is for use in determining time intervals that may be used for warranty purposes, etc, which is low-cost, safe, highly versatile, and reliable.
These and other features and aspects of the present embodiments will be more fully understood from the following detailed description of the preferred embodiments, which should be read in light of the accompanying drawings. It should be understood that both the foregoing generalized description and the following detailed description are exemplary, and are not restrictive of the invention.
In the exemplary embodiment, the indicator apparatus 100 is a label that is comprised of, preferably, a thin radiation emitting film 112 that is a source which emits essentially ionizing radiation. The thin ionizing radiation emitting film 112 may include a thin carrier foil layer 114 and a radiation emitting layer 116. In this embodiment, the carrier foil layer 114 is, preferably, made of a suitable metal, such as a nickel foil layer 114. The radiation emitting layer 116 may be a Ni-63 radionuclide film and may be applied by electroplating on one surface of the nickel foil layer 114 of the radiation emitting film 112. The thin nickel foil layer 114 may have a thickness on the order of about 0.5 mils and the radiation emitting layer 116 have a thickness on the order of about 10.0 mils. Other thicknesses may be used depending on the constituency of the radiation emitting layer 116 as well as the uses intended for the indicator apparatus. The radiation emitting layer 116 may be adapted to emit from a first surface 118, preferably, alpha and/or beta particles, although the present invention is not limited in scope to those specific particles. The radiation emitting layer 116 in this embodiment emits beta radiation having an energy in a range of about 5-75 keV, and, preferably, between about 17 to 66 keV. It will be appreciated that the scope of the invention embraces other radioactive strengths depending on the end uses envisioned. Emitted radioactive particles, such as alpha and beta particles, have a measurable and detectable half-life. One reason for utilizing alpha and/or beta particles is that they are generally of low strength and may be shielded relatively easily. In addition, alpha and/or beta particles at the radiation levels preferred do not otherwise pose a health radiation risk when used in the manner contemplated by this invention. The alpha and/or beta particles selected are capable of striking a radiation sensitive recording medium that is sensitive to ionizing radiation, such as a dosimetry film layer 130 and cause physical changes to the latter. Because commercial usage is contemplated, the radiation emitting film 112 contains a sufficient quantity of radioactive material that does not present any established health hazard risks, as determined by U.S. government agencies. The radiation emitting film 112 of this embodiment may be obtained commercially from several sources including Stuart Hunt and Associates, Toronto, Ontario, Canada, or Victoreen, Inc., Cleveland, Ohio, USA. The radiation emitting layer 116 is a formulation comprising a Ni-63 radionuclide layer (i.e., a nickel 63 isotope). Other suitable sources of ionizing radiation materials are contemplated, such as tritium, cesium 137, strontium 90, and americium 291. While the above embodiments disclose one type of radiation emitting film construction, the present invention contemplates a variety of radiation emitting materials. For instance, tritium is also a low-energy beta emitter that poses little health risk, but occurs primarily as tritiated water (T20). Successful use of tritium in the elapsed time apparatus requires replacement of the Ni-63 radionuclide layer with an aqueous dispersion of tritiated water in any suitable waterborne pressure sensitive adhesive.
A pair of pressure sensitive adhesive layers 120, 122 may be laminated to the opposing surfaces of the ionizing radiation emitting film 112 using conventional techniques and processes. The pressure sensitive adhesive layers 120, 122 may be made from any of a number of acrylic-based, rubber-based, or silicone-based double-sided adhesive transfer formulations, such as those available from 3M, St. Paul, Minn., USA or Adhesives Research, Glen Rock, Pa., USA. Clearly, other suitable materials may be utilized. The pressure sensitive adhesive layer 120 is utilized for purposes of minimizing or even eliminating penetration of the radioactive materials therethrough. Given the radiation strength being emitted by the radiation emitting film 112, the pressure sensitive adhesive layer 120 may have a thickness in the range of about 0.5-10 mils; preferably from about 1-2 mils. The pressure sensitive adhesive layer 122 has a relatively thinner thickness than the pressure sensitive adhesive layer 120. This is for permitting penetration of the beta particles into the radiation sensitive display or dosimetry film layer 130 when the two are mated in a juxtaposed overlying relationship during a period in which the radiation is to be measured (see
A release liner 124 having a suitable thickness is laminated to the pressure sensitive adhesive layer 122 in order to prevent premature adhesion of the first layer assembly 105 during shipping and storage. The release liner 124 is made from any suitable material, such as Kraft paper, polyester film, or vinyl film. A release liner 126 having a suitable thickness is laminated to pressure sensitive adhesive layer 120 in order to prevent premature adhesion during shipping and storage. The release liner 126 may also be made from any suitable material, such as Kraft paper, polyester film, or vinyl film. The thicknesses of the release layers may be in a range of about 1-10 mils; preferably about 3 mils. The thickness ranges are preferred because they tend to minimize or eliminate any undesired radiation from leaking. The thickness ranges of the pressure sensitive adhesive layers may also be taken into account for shielding. As such, the first layered assembly 105 of the indicator apparatus 100 is formed.
The second layer assembly 110 in the present embodiment includes a radiation sensitive display or dosimetry film layer 130. The radiation sensitive display or dosimetry film layer 130 may be a known dosimetry film in which changes in physical and chemical characteristics thereof occur in response and proportional to the incident dosage of radioactive materials, such as the beta particles. The dosimetry film layer 130 may be of the black and white type that is commercially available from, for example, Agfa or Kodak. In this embodiment, the dosimetry film layer 130 may have pressure sensitive adhesive layers 132, 134 laminated to opposing surfaces thereof. The pressure sensitive adhesive layers 132, 134 have thickness of about 1 mils to 10 mils; respectively. Again, the thicknesses are for controlling the attenuation of radioactive materials without comprising pliability and the adhesive characteristics thereof. The dosimetry film layer 130 may be laminated to a release liner 136 through the pressure sensitive adhesive layer 132. The pressure sensitive adhesive layer 132 may be made of a destructive type of adhesive material, such that it will cause destruction of the dosimetry film if the latter is removed from being mated to the radiation emitting film. The pressure sensitive adhesive layer 132 can be made of material similar to that for the pressure sensitive adhesive layers 120, 122. The strength of the adhesive for the pressure sensitive adhesive layer 132 is appropriately selected towards functioning as noted. The thickness of the radiation sensitive dosimetry film layer 130 is such that all of the emitted beta particles are, preferably, absorbed therein. The beta particles strike a first surface 131 of the dosimetry film layer 130. In addition, the risk of incidental exposure is further controlled and limited. In this embodiment, dosimetry film layer 130 may have a thickness of about 10 mils. Other suitable kinds of radiation sensitive materials and thicknesses may be applied depending on the circumstances encountered. In practice, the beta particles emitted from the radiation emitting film 112 strike the dosimetry film layer 130 causing the latter to darken proportionally to the incident dose of the beta radiation. As time elapses, a greater number of beta particles strike the dosimetry film layer 130 thereby causing it to continue darkening. The embodiment illustrated in
A protective element or overlay 138 essentially comprises an optically transparent film that is laminated to a top or second surface of the dosimetry film layer 130 (see
The protective element or overlay 138 is optically transparent for allowing direct reading by users or any automated equipment for reading the results. The protective overlay 138 may be made from any of a number of polymeric materials, including but not limited to, polycarbonate, polyvinyl chloride, polyethylene, polyester, and polypropylene. The protective overlay 138 is transparent and/or translucent to visually reveal the changes to the optical properties of the dosimetry film layer 130 as the dosage of beta particles changes. The progressive darkening intensities of the dosimetry film layer 130 are indicative of elapsed time. Measurement of the progressive darkening may be accomplished in a number of known ways both manually and/or automatically.
One exemplary approach utilizes a separate grayscale device 140 illustrated in
A low tack pressure sensitive adhesive layer 150 may be applied to either one or both of the first layer assembly 105 and the second layer assembly 110. The low tack pressure sensitive adhesive layer 150 may be applied to one or both release liners 124 and 126. In this embodiment, the pressure sensitive adhesive layer 150 is laminated on the release liner of the second layer assembly 110 by conventional techniques. As such, the second layer assembly 110 of the indicator apparatus 100 is formed. Towards this end, the low tack pressure sensitive adhesive layer 150 may be made from acrylic, silicone, and/or rubber based materials. The low tack pressure sensitive adhesive layer 150 may have a thickness in the range of 1-5 mils and should be sufficient to allow repeated peelings and laminations. The foregoing examples of materials for the low tack pressure sensitive adhesive layer 150 are non-limiting, insofar as a wide variety of materials may achieve the desired selective repeatable peel-apart aspects. The first and second layer assemblies 105, 110 are halves that may be joined together for shipping and/or mounting. The low tack pressure sensitive adhesive 150 provides for easy separation of the two halves of the indicator apparatus while the dual release liners, as noted, provide sufficient thickness to stop the beta particles from exposing the dosimetry film and otherwise halt undesired leakage of radiation.
Reference is made to
One exemplary process 800 of assembling and using the indicator apparatus 400 is set forth in
The embodiments and examples set forth herein were presented in order to best explain the present invention and its practical application and to thereby enable those skilled in the art to make and use the invention. However, those skilled in the art will recognize that the foregoing description and examples have been presented for the purposes of illustration and example only. The description as set forth is not intended to be exhaustive or to limit the invention to the precise form disclosed. Many modifications and variations are possible in light of the above teachings without departing from the spirit and scope of the following claims.
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Number | Date | Country | |
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20070058493 A1 | Mar 2007 | US |