US2873377A - Method of analyzing compositions - Google Patents

Method of analyzing compositions Download PDF

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US2873377A
US2873377A US477819A US47781954A US2873377A US 2873377 A US2873377 A US 2873377A US 477819 A US477819 A US 477819A US 47781954 A US47781954 A US 47781954A US 2873377 A US2873377 A US 2873377A
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/22—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material
    • G01N23/221—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material by activation analysis
    • G01N23/222—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material by activation analysis using neutron activation analysis [NAA]
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/03—Investigating materials by wave or particle radiation by transmission
    • G01N2223/04—Investigating materials by wave or particle radiation by transmission and measuring absorption
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/045—Investigating materials by wave or particle radiation combination of at least 2 measurements (transmission and scatter)
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/30—Accessories, mechanical or electrical features
    • G01N2223/303—Accessories, mechanical or electrical features calibrating, standardising
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/60—Specific applications or type of materials
    • G01N2223/635—Specific applications or type of materials fluids, granulates

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  • a method has' been devised which will provide an indication almost instantaneously of a change in concentration of an element in a'composition undergoing reaction. It is also contemplated that the method in addition to providing an indication of such a change, can be used to control-the process continuously and automatically so as to maintain, as far as possible, the desired concentrations of the elements.
  • the actual geometrical arrangement of the apparatus will vary depending upon the particular problem, but in general the apparatus will comprise a source of fast neutrons such as a mixture of radium and beryllium or polonium and trons will traverse material having the equivalent slowing down power of at least three inches of water.
  • Figs. 1, 2, and 3 illustrate diagrammatically sections through a vessel, pipe or the like showing three slightly difierent arrangements ofapparatus which can be used in carrying out the method, and
  • Figs. 4 and 5 are curves or rather families of curves which will serve to illustrate the method'which will 'be described in detail. hereinafter.
  • a portion of a vessel, pipe or the like 10 is shown as containing a fluid composition 12 or serving as a conduit for such a composition.
  • the container 10 may be assumed to have anexternal diameter of the order of aboutone foot.
  • 2A source of neutrons 14 is shown as positioned against orclose to the outer surface of the container and this source may comprise, for example, a mixture of radium and beryllium or a mixture of poloniumxand beryllium.
  • a detector 16 of thermal neutrons which may be of any suitable type such as a: boron trifluoride counter or a counter of which the 'wallsare coated with a thin layer or boron-carbide such as is disclosed in the aforementioned Herzog et al. Patent-No. 2,443,731.
  • Shown as disposedmore or less opposite the source 14 is another thermal neutron detector 18- generally similar to the detector 16.
  • the detectors 16 and '13 may be connected to suitable amplifying and indicating or recording apparatus, not. shown.
  • Fig. 4 the counting rates of the counters 16 and 18 are plotted as a function of the hydrogen density, the different sets ofcurves being obtained for different densities of chlorine, an element having a high capture cross section for thermal. neutrons.
  • the three curvesindicated by the bracket 16 show the variations in counting rate as the hydrogen concentration or density varies, the counting rate. beingmeasured at the detector 16.
  • the three curves marked by the bracket 18 show the variations in counting rate at detector 18 for difierent densities of hydrogen within the composition 12.
  • the composition measured contained different amounts of chlorine, these amounts or densities being-indicated arbitrarily by the figures 0, 1O, 20, etc.
  • t is to be understood that for a particular size or shape of container and for a particular geometrical arrangement of source and detector, fluids of known hydrogen and chloride concentrations can be placed in or passed ments hydrogen and chlorine but in unknown quantities or concentrations are placed within or passed through the container and the counting rates of the two detectors 16 and 18 are observed. Then with reference to the curves of Fig. the point of intersection of the two curves indicating the counting rates at the two detectors will give the densities both of thehydrogen and the chlorine in the composition in which their concentrations were previously not known.
  • the chart of Fig. 5 can be used in the following way to determine hydrogen and chlorine densities simultaneously.
  • the apparatus can take the form il lustrated in Fig. 2.
  • the composition 12 is within a container a perhaps several feet or more in diameter.
  • the neutron source 14a is shown as partially surrounded by a thermal neutron detector 16a on or close to the outer surface of the container 10a. In this case, however, the remote detector 18 of Fig.
  • FIG. 3 another form of apparatus is illustrated for use with large containers.
  • an elongated housing 22 is adapted to be inserted in a composition 12b within a container 10b as by insertion through the container wall or by being suspended from a cable or the like.
  • a neutron source 14b shown as surrounded by a thermal neutron detector 16b.
  • Two other similar thermal neutron detectors 18b and 20b are also disposed within the housing 22 at opposite sides of the detector 16b and separated from the source 14b by a distance such that some of the neutrons from the source in reaching the detectors 18b and 2% will traverse an amount of the composition 1212 having the equivalent slowing down power of at least three inches of water.
  • the detector 16b will be connected to a suitable amplifying and indicating or recording device, not shown, and also that the two detectors 18b and 20b will both'be connected to another suitable amplifying and indicating or recording device, not shown.
  • the operation with the apparatus described in Fig. 3 will be substantially the same as those described in Fig. 2 and referencewill be made to calibration curves similar to those in Figs. 4 and 5 both plotted from data obtained with a fluid or fluids of known hydrogen and chlorine concentrations which are present within the container 10b.
  • the outputs of the thermal neutron detectors can be made to actuate inlet or outlet valves or the like so as to control the concentration of one or more elements within the composition.
  • the neutron source may be surrounded by a moderating material such as parrafiin, heavy water, carbon or the like and only one detector used and placed at such a distance from the source so that the absorption of the thermal neutrons can be observed, this absorption being 'dependent upon the concentration of an element such as boron or the like, such elements having a large thermal neutron capture cross section.
  • a moderating material such as parrafiin, heavy water, carbon or the like
  • shields of, say, cadmium may be used to reduce the numher of thermal neutrons which might pass from the new tron source directly to the detector without passing through,the substance being analyzed.
  • the source-todetector distance would of course be considerably greater than when a neutron counter is used and it would be necessary to have an efficient gamma ray shield such as several inches of tungsten or lead around the source if a gamma ray-emitting source such as a mixture of radium and beryllium is used.
  • this method provides prompt means for determining the progress ofthe hydrogenation of vegetable oils.
  • the method of determining changes in the concentrations of two elements in a material in a Vessel which comprises first bombarding with neutrons in said vessel a similar material containing known concentrations of said elements, simultaneously measuring the counting rates of thermal neutrons passing through different distances in said similar material, plotting a family of crossed curves showing the variation in density of each of said elements in said similar material as a function of the variations in density of another of said elements for predetermined different counting rates at each of said distances, repeating the aforementioned steps of bombarding with neutrons and measuring thermal neutrons with said first mentioned material in said vessel to obtain the counting rates at said two distances, and then referring to said curves to obtain the densities of said elements in the first mentioned material, the points of intersection of the curves for the counting rates subsequently obtained at said diiferent distances with the first mentioned material constituting an indication of the densities of the two elements being measured.
  • one of said elements is an element having a low capture cross section for thermal neutrons and the other is an element having a high capture cross section for thermal neutrons.
  • An apparatus for measuring the concentrations of two elements in a fluid composition contained in a vessel comprising an elongated housing adapted to be inserted in said composition within the vessel, 2. source of neutrons within said housing, a detector of thermal neutrons within said housing in the immediate vicinity of said source and at least one other similar thermal neutron detector in said housing and spaced from said source by a distance such that neutrons measured thereby will have traversed an amount of said composition having the equivalent slowing down power of at least three inches of water.
  • the method of determining the concentrations of elements in a material in a vessel which comprises irradiating with neutrons a plurality of samples of said material containing diiierent known concentrations of said elements while measuring the counting rates of thermal neutrons detected after passing through different distances in said material and recording said counting rates of neutrons detected at the respective distances in correlation with the relative concentrations of said elements in order to provide calibration data, irradiating with neutrons an unknown sample to determine the concentrations of said materials contained therein while detecting and measuring the counting rates of thermal neutrons detected after passing through the said plurality of distances and comparing said counting rates at the respective distances with the calibration data to determine the concentrations of each of said elements in said sample.
  • one of said elements is an element having a low capture cross section for thermal neutrons and the other is an element having a high capture cross section for thermal neutrons.

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  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
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Description

' Feb. 10, 1959 A. s. MCKAY 2,873,377
METHOD OF ANALYZING COMPOSITIONS Filed Dec. 27, 1954 (20/2/17! rafe United METHOD OF ANALYZING COMPOSITIONS Alexander S. McKay, Bellair'e, Tex., assignor to'The Tex'as Company, New York, N. Y., a corporation of flelaware Application December 27, 1954, Serial-No. 477,819 16 Claims. or. 250-435 This invention relates to a method ofanalyzing compositions and more particularly to a method-involving. .the use of radioactivity measurements for determining the proportions or concentrations of elements present in a chemical compound, mixture or the like. The princi palobject of the invention is the provision of a method of this type which is convenient and efiective in situations where it is difficult, if not impossible, to have direct access to the material to be analyzed. i
It is well known that there are frequentlyv great diificulties in determining the relative proportions. of various elements which are present in a composition under the conditions of high temperature, pressure and corrosion which exist in many chemical industrial processes. By way of example, this is very true in the oil refining industry where mixtures of oil, acid and the like are being treated under conditions of very high temperature and pressure, such as in hydrogenation for instance. Due to the high" pressures involved the hot compositions 'are contained in or passed through vessels or pipes, the walls of which must be of considerable thickness and this factor renders it still more difficult to obtain easy access to the composition to be examined. There are many instances where the proportions of the elements in such acomposition mayvary during reaction and it is, of
course, very important that such a change or variation in concentration be quickly determined.
In accordance with the invention, a method has' been devised which will provide an indication almost instantaneously of a change in concentration of an element in a'composition undergoing reaction. It is also contemplated that the method in addition to providing an indication of such a change, can be used to control-the process continuously and automatically so as to maintain, as far as possible, the desired concentrations of the elements. As will be explained hereinafter, the actual geometrical arrangement of the apparatus will vary depending upon the particular problem, but in general the apparatus will comprise a source of fast neutrons such as a mixture of radium and beryllium or polonium and trons will traverse material having the equivalent slowing down power of at least three inches of water.
For a better understanding of the invention, reference may be had to the accompanying drawing in which:
Figs. 1, 2, and 3 illustrate diagrammatically sections through a vessel, pipe or the like showing three slightly difierent arrangements ofapparatus which can be used in carrying out the method, and
Figs. 4 and 5 are curves or rather families of curves which will serve to illustrate the method'which will 'be described in detail. hereinafter.
Referring. to the drawing, in the somewhat diagrammatic illustration of Fig. 1 a portion of a vessel, pipe or the like 10 is shown as containing a fluid composition 12 or serving as a conduit for such a composition. The container 10 may be assumed to have anexternal diameter of the order of aboutone foot. 2A source of neutrons 14 is shown as positioned against orclose to the outer surface of the container and this source may comprise, for example, a mixture of radium and beryllium or a mixture of poloniumxand beryllium. At least in the immediate vicinity of and shown as partly surrounding the source 14 is a detector 16 of thermal neutrons which may be of any suitable type such as a: boron trifluoride counter or a counter of which the 'wallsare coated with a thin layer or boron-carbide such as is disclosed in the aforementioned Herzog et al. Patent-No. 2,443,731. Shown as disposedmore or less opposite the source 14 is another thermal neutron detector 18- generally similar to the detector 16. The detectors 16 and '13 may be connected to suitable amplifying and indicating or recording apparatus, not. shown.
Some of thefastneutrons from the source 14 willpass into the composition 12 within the container wherein they will be slowed down so that they will reach the detector 18 in the thermal. neutron range. At the same time others of the fast neutrons will enter the composition.12 wherein they will be slowed down and scattered, some of them returning so as to be intercepted bythe detector 16. The counting rates of the two counters: or detectors 16 and 18 can be calibrated so that between them both the density: of hydrogen and the density of some element with a high capture cross section for thermal neutrons can be determined. Sample calibration curves are indicated in Figs. 4 and 5 of the drawing.
In Fig. 4 the counting rates of the counters 16 and 18 are plotted as a function of the hydrogen density, the different sets ofcurves being obtained for different densities of chlorine, an element having a high capture cross section for thermal. neutrons. The three curvesindicated by the bracket 16 show the variations in counting rate as the hydrogen concentration or density varies, the counting rate. beingmeasured at the detector 16. Likewise, the three curves marked by the bracket 18 show the variations in counting rate at detector 18 for difierent densities of hydrogen within the composition 12. In each case, the composition measured contained different amounts of chlorine, these amounts or densities being-indicated arbitrarily by the figures 0, 1O, 20, etc.
It will be seen that an increase. in chlorine density decreases the counting rate of both counters and it will also be observed from the shapes of the curves that it is'possible to keep the counting rate at detector 16 constant bysimultaneously increasing both the hydrogen and chlorine densities. Similarly, the counting rate at detector 18 may be kept constant if one decreases the hydrogen density and at the same time increases the chlorine density.
Since the counting rates at the two detectors can be kept constant by changing the concentrations of the two elements, the curves of Fig. 5 can be plotted, these curves showing hydrogen density as a function of chlorine density for several different counting rates at the two detectors 16 and 18.
t is to be understood that for a particular size or shape of container and for a particular geometrical arrangement of source and detector, fluids of known hydrogen and chloride concentrations can be placed in or passed ments hydrogen and chlorine but in unknown quantities or concentrations are placed within or passed through the container and the counting rates of the two detectors 16 and 18 are observed. Then with reference to the curves of Fig. the point of intersection of the two curves indicating the counting rates at the two detectors will give the densities both of thehydrogen and the chlorine in the composition in which their concentrations were previously not known. By way of example, the chart of Fig. 5 can be used in the following way to determine hydrogen and chlorine densities simultaneously. Assuming that detector 16 gives a counting rate of 300 counts per minute and that detector 18 gives a counting rate of 250 counts per minute, this will indicate only one possible hydrogen density and only one possible chlorine density as shown in Fig. 5 by the point where the 300 C. P. M. curve for detector 16 intersects the 250 C. P. M. curve for detector 18. This method of analysis is quite accurate provided that the other elements present in the composition are heavier than carbon and also have small capture cross sections for thermal neutrons or else that they are present with constant densities.
In the case of a fluid composition undergoing reaction or merely contained in or being passed through a container or conduit considerably greater than one or two feet in diameter, the apparatus can take the form il lustrated in Fig. 2. In this embodiment the composition 12:: is within a container a perhaps several feet or more in diameter. As in the case of Fig. 1, the neutron source 14a is shown as partially surrounded by a thermal neutron detector 16a on or close to the outer surface of the container 10a. In this case, however, the remote detector 18 of Fig. 1 is replaced by two thermal neutron detectors 18a and 20, these detectors being placed at the same side of the container as the detector 18a and separated from the source 14a by a distance such that some of the neutrons from the source will traverse a sufficient amount of the composition 12a to have the equivalent slowing down power of at least three inches of water. In making an analysis with the apparatus of Fig. 2 the operation and the use of the curves of Figs. 4 and 5 will be the same as has been described with reference to Fig. 1. Due, however, to the difference in size of the container and the difierent geometrical arrangement of the detectors and source, the curves of Figs. 4 and 5 will, of course, not be exactly the same as when the apparatus of Fig. 1 is used. Nevertheless, the curves will be generally similar and their use will be the same as that already described. It is also to be understood that there may be situations where both detectors 18a and will not be needed, either one alone being sufiicient.
. In Fig. 3 another form of apparatus is illustrated for use with large containers. In this embodiment an elongated housing 22 is adapted to be inserted in a composition 12b within a container 10b as by insertion through the container wall or by being suspended from a cable or the like. Within the housing 22 is a neutron source 14b shown as surrounded by a thermal neutron detector 16b.
Two other similar thermal neutron detectors 18b and 20b are also disposed within the housing 22 at opposite sides of the detector 16b and separated from the source 14b by a distance such that some of the neutrons from the source in reaching the detectors 18b and 2% will traverse an amount of the composition 1212 having the equivalent slowing down power of at least three inches of water. Again, although it is preferable to use the two detectors 18b 'and 20b, one alone may sufiice when space limitations arise. It is understood that the detector 16b will be connected to a suitable amplifying and indicating or recording device, not shown, and also that the two detectors 18b and 20b will both'be connected to another suitable amplifying and indicating or recording device, not shown. The operation with the apparatus described in Fig. 3 will be substantially the same as those described in Fig. 2 and referencewill be made to calibration curves similar to those in Figs. 4 and 5 both plotted from data obtained with a fluid or fluids of known hydrogen and chlorine concentrations which are present within the container 10b.
While in the previous explanation, reference has been made only to the use of this method for obtaining an indication of the densities of two elements in a composition, it is to be understood that with suitable additional apparatus the outputs of the thermal neutron detectors can be made to actuate inlet or outlet valves or the like so as to control the concentration of one or more elements within the composition.
In some situations where there is either none or a very small amount of hydrogen or other substance containing light atoms present, the neutron source may be surrounded by a moderating material such as parrafiin, heavy water, carbon or the like and only one detector used and placed at such a distance from the source so that the absorption of the thermal neutrons can be observed, this absorption being 'dependent upon the concentration of an element such as boron or the like, such elements having a large thermal neutron capture cross section. In this case,
shields of, say, cadmium may be used to reduce the numher of thermal neutrons which might pass from the new tron source directly to the detector without passing through,the substance being analyzed.
It would also be possible to use a gamma ray detector instead of a thermal neutron detector in the case where capture cross section.
only the remote detector is required. The source-todetector distance would of course be considerably greater than when a neutron counter is used and it would be necessary to have an efficient gamma ray shield such as several inches of tungsten or lead around the source if a gamma ray-emitting source such as a mixture of radium and beryllium is used.
Oneof the most obvious applications of this invention is in the halogenation process. Curves similar to those of Figs. 4 and 5 could be used for chlorine, bromine or iodine to determine the amount of hydrogen that has been replaced in the original organic molecule. The amount of fluorination could also be determined indirectly by observing the hydrogen density. The presence of the fluorine itself would have little effect on the counting rates because of its small capture cross section for thermal neutrons.
Another application is in the glass industry. The properties of certain glasses such as Pyrex depend critically upon the amount of boron which is present. With this invention, it is very easy to measure the amountof boron in the presence of the other glass atoms which are mainly oxygen and silicon and other elements of low One would therefore be able to obtain an accurate determination of the amount of'boron present by simply observing the absorption of thermal neutrons by the hot glass mixture.
With the method described, one can also control hydrogenation progress. For instance, this method provides prompt means for determining the progress ofthe hydrogenation of vegetable oils. 7
Obviously many other modifications and variations of the invention as hereinbefore set forth may be made without departing from the spirit and scope thereof, and therefore only such limitations should be imposed as are indicated in the appended claims.
I claim: a
1. The method of determining changes in the concentrations of two elements in a material in a Vessel, which comprises first bombarding with neutrons in said vessel a similar material containing known concentrations of said elements, simultaneously measuring the counting rates of thermal neutrons passing through different distances in said similar material, plotting a family of crossed curves showing the variation in density of each of said elements in said similar material as a function of the variations in density of another of said elements for predetermined different counting rates at each of said distances, repeating the aforementioned steps of bombarding with neutrons and measuring thermal neutrons with said first mentioned material in said vessel to obtain the counting rates at said two distances, and then referring to said curves to obtain the densities of said elements in the first mentioned material, the points of intersection of the curves for the counting rates subsequently obtained at said diiferent distances with the first mentioned material constituting an indication of the densities of the two elements being measured.
2. The method described in claim 1 in which one of said measurements is made in the immediate vicinity of the source of neutrons.
3. The method described in claim 2 in which the other measurement is made at such a distance from the source of neutrons that the neutrons measured will have traversed material having the equivalent slowing down power of at least three inches of water.
4. The method described in claim 1 in which one of said elements is hydrogen and the other is an element having a high capture cross section for thermal neutrons.
5. The method described in claim 1 in which one of said elements is hydrogen and the other is chlorine.
6. The method described in claim 1 in which one of said elements is an element having a low capture cross section for thermal neutrons and the other is an element having a high capture cross section for thermal neutrons.
7. The method described in claim 6 in which the ele ment having the high capture cross section is boron.
3. An apparatus for measuring the concentrations of two elements in a fluid composition contained in a vessel comprising an elongated housing adapted to be inserted in said composition within the vessel, 2. source of neutrons within said housing, a detector of thermal neutrons within said housing in the immediate vicinity of said source and at least one other similar thermal neutron detector in said housing and spaced from said source by a distance such that neutrons measured thereby will have traversed an amount of said composition having the equivalent slowing down power of at least three inches of water.
9. An apparatus as defined in claim 8 in which two of said similar thermal neutron detectors are disposed in said housing at opposite sides from the detector which is in the immediate vicinity of the source, each of said other detectors being spaced from the source as defined in claim 8.
10. The method of determining the concentrations of elements in a material in a vessel which comprises irradiating with neutrons a plurality of samples of said material containing diiierent known concentrations of said elements while measuring the counting rates of thermal neutrons detected after passing through different distances in said material and recording said counting rates of neutrons detected at the respective distances in correlation with the relative concentrations of said elements in order to provide calibration data, irradiating with neutrons an unknown sample to determine the concentrations of said materials contained therein while detecting and measuring the counting rates of thermal neutrons detected after passing through the said plurality of distances and comparing said counting rates at the respective distances with the calibration data to determine the concentrations of each of said elements in said sample.
11. The method described in claim 10 in which one of said measurements is made in the immediate vicinity of the source of neutrons.
12. The method described in claim 11 in which the other measurement is made at such a distance from the source of neutrons that the neutrons measured will have traversed material having the equivalent slowing down power of at least three inches of water.
13. The method described in claim 10 in which one of said elements is hydrogen and the other is an element having a high capture cross section for thermal neutrons.
14. The method described in claim 10 in which one of said elements is hydrogen and the other is chlorine.
15. The method described in claim 10 in which one of said elements is an element having a low capture cross section for thermal neutrons and the other is an element having a high capture cross section for thermal neutrons.
16. The method described in claim 15 in which the element having the high capture cross section is boron.
Refiereuces Cited in the file of this patent UNITED STATES PATENTS

Claims (2)

1. THE METHOD OF DETERMINING CHANGES IN THE CONCENTRATIONS OF TWO ELEMENTS IN A MATERIAL IN A VESSEL, WHICH COMPRISES FIRST BOMBARDING WITH NEUTRONE IN SAID VESSEL A SIMILAR MATERIAL CONTAINING KNOWN CONCENTRATIONS OF SAID ELEMENTS, SIMULTANEOUSLY MEASURING THE COUNTING RATES OF THERMAL NEUTRONE PASSING THROUGH DIFFERENT DISTANCES IN SAID SIMULAR MATERIAL, PLOTTING A FAMILLY OF CROSSED CURVES SHOWING THE VARIATION IN DENSITY OF EACH OF SAID ELEMENTS IN SAID SIMULAR MATERIAL AS A FUNCTION OF THE VARIATIONS IN DENSITY OF ANOTHER OF SAID ELEMENTS FOR PREDETERMINED DIFFERENT COUNTING RATES AT EACH OF SAID DISTANCES, REPEATING THE AFOREMENTIONED STEPS OF BOMBARDING WITH NEUTRONS AND MEASURING THERMAL NEUTRONS WITH SAID FIRST MENTION MATERIAL IN SAID VESSEL TO OBTAIN THE CONTING RATES AT SAID TWO DISTANCES, AND THEN REFERRING TO SAID CURVES TO OBTAIN THE DENSITIES OF SAID ELEMENTS IN THE FIRST MENTIONED MATERIAL, THE POINTS INTERSECTION OF THE CURVES FOR THE COUNTING RATES SUBSEQUENTLY OBTAINED AT SAID DIFFERENT DISTANCES WITH THE FIRST MENTIONED MATERIAL CONSTITUTING AN INDICATION OF THE DENSITIES OF THE TWO ELEMENTS BEING MEASURED.
8. AN APPARATUS FOR MEASURING THE ONCENTRATION OF TWO ELEMENTS IN A FLUID COMPOSITION CONTAINED IN A VESSEL COMPRISING AN ELONGATED HOUSING ADAPTED TO BE INSERTED IN SAID COMPOSITION WITHIN THE VESSEL, A SOURCE OF NEUTRONS WITHIN SAID HOUSING A DETECTOR OF THERMALNEUTRONS WITHIN SAID HOUSING IN THE IMMEDIATE VICINITY OF SAID SOURCES AND AT LEAST ONE OTHER SIMULAR THERMAL NEUTRON DECTORS IN SAID HOUSING AND SPACES FROM SAID SOURCE BY A DISTANCE SUCH THAT NEUTRONS MEASURED THEREBY WILL HAVE TRAVERSED AN AMOUNT OF SAID COMPOSITION HAVING THE EQUIVALENT SLOWING DOWN POWER OF AT LEAST THREE INCHES OF WATER.
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Cited By (30)

* Cited by examiner, † Cited by third party
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US2978581A (en) * 1956-11-20 1961-04-04 Robertshaw Fulton Controls Co Radiant energy detection device
US3009062A (en) * 1956-12-05 1961-11-14 Jr William A Brooksbank Absorption analyzer
US3025396A (en) * 1958-09-22 1962-03-13 Singer Inc H R B Radioisotope pressure transducer
US3082323A (en) * 1958-06-25 1963-03-19 Ind Nuclconics Corp Radiation analysis
US3088026A (en) * 1958-12-22 1963-04-30 Jersey Prod Res Co Fluid entry analyzer
US3100840A (en) * 1958-04-14 1963-08-13 Nuclear Corp Of America Inc Methods and apparatus for measuring and testing
US3124679A (en) * 1964-03-10 Nuclear determination of
US3200251A (en) * 1961-07-07 1965-08-10 Well Surveys Inc Apparatus for neutron-neutron well logging
US3213280A (en) * 1960-08-24 1965-10-19 Gen Motors Corp Method and apparatus for measuring hydrogenous material
US3239663A (en) * 1961-12-04 1966-03-08 Dresser Ind Velocity measurement utilizing neutron activation of oxygen
US3254210A (en) * 1961-08-16 1966-05-31 Gen Dynamics Corp Method for determining organically bound halide in a liquid
US3254212A (en) * 1962-01-12 1966-05-31 Continental Oil Co Apparatus for determining the concentration of aluminum in hydrocarbon streams by the use of k-capture radioactivity
US3293434A (en) * 1963-10-17 1966-12-20 Arthur H Dexter Photoneutron monitor for detecting reactor fuel element failures
US3350561A (en) * 1962-06-20 1967-10-31 Rheinische Kalksteinwerke Moisture content measurement having neutron reflecting material to provide optimum counting range
US3353021A (en) * 1964-09-29 1967-11-14 Robert F Stewart Apparatus and process for continuous measurement of moisture in moving coal by neutron thermalization
DE1288341B (en) * 1960-03-12 1969-01-30 Well Completions Inc Method and device for the detection of chemical elements in a sample consisting of granular components
US3437809A (en) * 1965-07-06 1969-04-08 Gulf Research Development Co Neutron transmission method of analysis and apparatus therefor
US3461286A (en) * 1968-05-23 1969-08-12 Atomic Energy Commission Method and apparatus for measuring the void fraction of hydrogenous fluids
US3463920A (en) * 1965-08-31 1969-08-26 Simmonds Precision Products Cryogenic fuel gauging apparatus utilizing neutron absorption techniques
US3555274A (en) * 1967-04-26 1971-01-12 North American Rockwell Radiation measurement instrument using scatter radiation
US3577158A (en) * 1969-01-07 1971-05-04 Industrial Nucleonics Corp Mass flow rate measuring utilizing the scattering cross section of a material for fast neutrons
US3600574A (en) * 1969-05-12 1971-08-17 Gen Motors Corp Radiometric method and apparatus for measuring and controlling foundry sand moisture
US3787682A (en) * 1966-10-21 1974-01-22 Vdo Schindling Apparatus for measuring the filling level in liquid receiving containers by means of radio-active rays
US3794836A (en) * 1971-03-25 1974-02-26 Zinc Corp Ltd Immersible absorption probe
US4027163A (en) * 1974-01-25 1977-05-31 Sagami Chemical Research Center Method of compensating for quenching effect of substance contained in a sample gas the radioactivity of which is to be measured by a radioactivity detector and apparatus for performing the same
US4038548A (en) * 1974-06-21 1977-07-26 Imperial Chemical Industries Limited Level and interface detection
DE3107327A1 (en) * 1980-03-06 1981-12-24 Texaco Development Corp., 10650 White Plains, N.Y. "METHOD AND DEVICE FOR DETERMINING THE SALT AND SULFUR CONTENT OF A LIQUID"
US4924099A (en) * 1986-12-15 1990-05-08 Exxon Production Research Company Method and apparatus for monitoring a flowstream
US5300781A (en) * 1991-12-09 1994-04-05 Kay-Ray/Sensall, Inc. Non-hydrogenous process level measurement
US5866899A (en) * 1996-09-12 1999-02-02 Advanced Micro Devices, Inc. Concentration measurement apparatus calibration method

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Cited By (31)

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US3124679A (en) * 1964-03-10 Nuclear determination of
US2978581A (en) * 1956-11-20 1961-04-04 Robertshaw Fulton Controls Co Radiant energy detection device
US3009062A (en) * 1956-12-05 1961-11-14 Jr William A Brooksbank Absorption analyzer
US3100840A (en) * 1958-04-14 1963-08-13 Nuclear Corp Of America Inc Methods and apparatus for measuring and testing
US3082323A (en) * 1958-06-25 1963-03-19 Ind Nuclconics Corp Radiation analysis
US3025396A (en) * 1958-09-22 1962-03-13 Singer Inc H R B Radioisotope pressure transducer
US3088026A (en) * 1958-12-22 1963-04-30 Jersey Prod Res Co Fluid entry analyzer
DE1288341B (en) * 1960-03-12 1969-01-30 Well Completions Inc Method and device for the detection of chemical elements in a sample consisting of granular components
US3213280A (en) * 1960-08-24 1965-10-19 Gen Motors Corp Method and apparatus for measuring hydrogenous material
US3200251A (en) * 1961-07-07 1965-08-10 Well Surveys Inc Apparatus for neutron-neutron well logging
US3254210A (en) * 1961-08-16 1966-05-31 Gen Dynamics Corp Method for determining organically bound halide in a liquid
US3239663A (en) * 1961-12-04 1966-03-08 Dresser Ind Velocity measurement utilizing neutron activation of oxygen
US3254212A (en) * 1962-01-12 1966-05-31 Continental Oil Co Apparatus for determining the concentration of aluminum in hydrocarbon streams by the use of k-capture radioactivity
US3350561A (en) * 1962-06-20 1967-10-31 Rheinische Kalksteinwerke Moisture content measurement having neutron reflecting material to provide optimum counting range
US3293434A (en) * 1963-10-17 1966-12-20 Arthur H Dexter Photoneutron monitor for detecting reactor fuel element failures
US3353021A (en) * 1964-09-29 1967-11-14 Robert F Stewart Apparatus and process for continuous measurement of moisture in moving coal by neutron thermalization
US3437809A (en) * 1965-07-06 1969-04-08 Gulf Research Development Co Neutron transmission method of analysis and apparatus therefor
US3463920A (en) * 1965-08-31 1969-08-26 Simmonds Precision Products Cryogenic fuel gauging apparatus utilizing neutron absorption techniques
US3787682A (en) * 1966-10-21 1974-01-22 Vdo Schindling Apparatus for measuring the filling level in liquid receiving containers by means of radio-active rays
US3555274A (en) * 1967-04-26 1971-01-12 North American Rockwell Radiation measurement instrument using scatter radiation
US3461286A (en) * 1968-05-23 1969-08-12 Atomic Energy Commission Method and apparatus for measuring the void fraction of hydrogenous fluids
US3577158A (en) * 1969-01-07 1971-05-04 Industrial Nucleonics Corp Mass flow rate measuring utilizing the scattering cross section of a material for fast neutrons
US3600574A (en) * 1969-05-12 1971-08-17 Gen Motors Corp Radiometric method and apparatus for measuring and controlling foundry sand moisture
US3794836A (en) * 1971-03-25 1974-02-26 Zinc Corp Ltd Immersible absorption probe
US4027163A (en) * 1974-01-25 1977-05-31 Sagami Chemical Research Center Method of compensating for quenching effect of substance contained in a sample gas the radioactivity of which is to be measured by a radioactivity detector and apparatus for performing the same
US4038548A (en) * 1974-06-21 1977-07-26 Imperial Chemical Industries Limited Level and interface detection
DE3107327A1 (en) * 1980-03-06 1981-12-24 Texaco Development Corp., 10650 White Plains, N.Y. "METHOD AND DEVICE FOR DETERMINING THE SALT AND SULFUR CONTENT OF A LIQUID"
US4365154A (en) * 1980-03-06 1982-12-21 Texaco Inc. Detection of impurities in a fluid containing free gas using nuclear techniques
US4924099A (en) * 1986-12-15 1990-05-08 Exxon Production Research Company Method and apparatus for monitoring a flowstream
US5300781A (en) * 1991-12-09 1994-04-05 Kay-Ray/Sensall, Inc. Non-hydrogenous process level measurement
US5866899A (en) * 1996-09-12 1999-02-02 Advanced Micro Devices, Inc. Concentration measurement apparatus calibration method

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