CA1067212A - Interface detection by neutron scattering - Google Patents

Interface detection by neutron scattering

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Publication number
CA1067212A
CA1067212A CA256,527A CA256527A CA1067212A CA 1067212 A CA1067212 A CA 1067212A CA 256527 A CA256527 A CA 256527A CA 1067212 A CA1067212 A CA 1067212A
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CA
Canada
Prior art keywords
detector
source
pipeline
detectors
wall
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
CA256,527A
Other languages
French (fr)
Inventor
Allan R. De Monchy
Cornelis A. Kok
Jan Dorrepaal
Johan A. Van Klaveren
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Shell Canada Ltd
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Shell Canada Ltd
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Filing date
Publication date
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Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01FMEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
    • G01F23/00Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm
    • G01F23/22Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water
    • G01F23/28Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water by measuring the variations of parameters of electromagnetic or acoustic waves applied directly to the liquid or fluent solid material
    • G01F23/284Electromagnetic waves
    • G01F23/288X-rays; Gamma rays or other forms of ionising radiation

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  • Physics & Mathematics (AREA)
  • Electromagnetism (AREA)
  • Thermal Sciences (AREA)
  • Fluid Mechanics (AREA)
  • General Physics & Mathematics (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
  • Measurement Of Radiation (AREA)

Abstract

A method for detecting an interface of materials having different hydrogen content, present in a metal vessel or pipe, e.g. made of steel in which near or at the outerside of the steel wall are present at least one neutron source and at least one neutron detector the distance between source and detector not being larger than 50 cm, the detector having a larger sensitivity for scattered neutrons than for neutrons emitted by the source, in which the neutron source consists of californium-252.

Description

106~Z~z The invention relates to a method and apparatus for detec-ting an interface of materials having different hydrogen content, present in a metal vessel or pipe, e.g. made of steel.
Interfaces as indicated above occur frequently in the pro-cess industry. Examples are levels of liquid hydrocarbons in settlers, in absorption columns, in distillation columns, interfaces in pipelines for gas transport if two-phase flow occurs, etc. Walls of columns, reactors, pipe-lines and the like are usually of steel and it has always been of importance to have available detection methods which do not require special constructions on the steel walls such as sight glasses, lead-in wires for measuring equip-ment, etc.
It is known to use the gamma-ray absorption method for de-tecting interfaces. This method, however, has a number of disadvantages.
G = a rays are absorbed far more strongly by steel than by hydrocarbons, so this method could only cope with large quantities of hydrocarbons behind steel walls. Furthermore, the gamma-ray source and the detector have to be placed in opposite positions on the container. Larga units will require large gamma sources the handling of which is cumbersome for safety reasons. To align a gamma source and detector in opposite positions a special construction along the container is needed. In addition it is often difficult to find a free optical path for the gamma rays if stirrers, baffles, trays etc. are present.
The invention provides apparatus which does not suffer from these dis-advantages.
According to the present invention, there is provided apparatus for detecting an interface of materials having different hydrogen content, present in an enclosed room, provided with at least one neutron source and at least one neutron detector, which is situated at a certain distance from said neutron source, wherein the enclosed room is a metal walled vessel or pipe to be used in process industry, and wherein the neutron source which consists of californium-252 and the detector are located near or at the outer-side of the metal wall of the vessel or pipe, said distance between source and detector not being larger than 50 cm, and the detector(s) having a larger sensitivity for scattered neutrons than for neutrons emitted by the source.

~ -2-i7Z~Z

The present invention provides a method for detecting an interface of materials having different hydrogen content, present in a steel vessel or pipe, in which near or at the outer side of the -2a-1~67Z~Z

steel wall are present at least one neutron source and at least one neutron detector, the distance between source and detector not being larger than 50 cm, the detector having a larger sensitivity scattered neutrons than for neutrons emitted by the source, in which the neutron source consists of californium-252.
This method is based on the fact that neutrons are transmitted through layers of steel and other heavy metals about as easily as light through a glass window, but are strongly scattered by the light hydroeen nuclei abundantly present in hydrocarbons or in water. When a suitable source and a detector that picks up the scattered neutrons are placed in appropriate locations outside the vessel amounts of hydrocarbons or water in the vessel as small as a few grams can thus be traced from behind a five centimetre steel wall and this is sufficient to detect the pres¢nce of an interface. Such an interface may be liquid hydrocarbons against their vapours or air or other gases, water against its vapour or air or other gases, the level of pulverulant solid organic material containing hydrogen. The method does not detect an interface between liquid hydrocarbons and water, because of the comparable hydrogen content of these liquids.
Californium-252 is a man-made transuranium isotope with a half value time of 2.7 year. This nuclide produces neutrons by spontaneous fission with a yield of 2.3x10 neutrons per second per microgram.
A source containing about 0.1-1 microgram produces sufficient neutrons for most technical applications. The dose rate from al~g-source having an activity of about 0.5 mCi at 1 m distance in air is within the limit of 2.5 millirem per hour, permit-ted for daily exposure of the 1067~1Z
radiological worker. This makes safe handling rather simple in comparison with most gamma-radiation sources generally used in the process industry. Most other neutron sources have much lower neutron yields and therefore sources of much larger activities are needed than Cf-252 which make the applications in process industries of other type neutron sources like Am-241-Be less attractive.
In a counting tube filled with helium-3 at a pressure of about 10 bar an uncharged neutron is conver-ted by a reaction with He-3 into a tritium nucleus and a proton with a total kinetic energy of 764 keV. The charged particles produce an electron avalanche between the wire-shaped anode (at a potential of 2000 V) and the cathode or wall of the tube. The avalanches produce current pulses which are counted by appropriate equipment. Such a detector is very sensitive for scattered neutrons which owing to the collisions with hydrogen they made have energies somewhere between the thermal energy distri-bution and that of fast neutrons from the source. The detector has a lower sensitivity for fast neutrons. It is therefore possible for the detector to be in the neighbourhood of the source. The detector receives scattered neutrons and a much larger number of fast neutrons from the source, which cannot be shielded from radiation directly to the detector. Owing to the properties of the detector as indicated above this creates no problem.
The intensity of the scattered neutrons decreases by increasing distance from the source and it is therefore of importance that the distance between source and detector is not larger than 50 cm and preferably not larger than 25 cm. This improves the sensitivity of the detection. For measurements on vessels with large diameters use is made mainly of returning neutrons by positioning the source and the detector close to each other one side of the vessel. This avoids special constructions on opposite sides of the vessel as 1~67Z12 i9 required for gamma-ray absorption with the accompanying problems of alignment.
An attractive possibility is to locate source and detector in such a way that the centre of gravity of both are in a plane which is perpendicular to the centre line of the vessel or pipe.
This may be achieved by positioning source and detector along a circle line against the outside of the steel wall of a vessel.
The two components may then be combined in one probe which can be moved alongthatwall. Another possibility is to position the source and the detector behind each other, the source being nearest to the wall. Both geometries have the advantage of sharp detec-tion of levels in a vessel or column and the combination of source and detector in one probe promotes ease of handling.
Notwithstanding that the dose rate of a Californium-252 source i5 already very low, it may be further decreased by means of a shielding.
The apparatus suitable for use in the method according to the invention therefore comprises a neutron source of Californium-252, a detector having a larger sensitivity for scattered neutrons than for neutrons emitted by the source? a shielding enveloping said detector and source at least partly, which shielding consists of a reflector~ a moderator and a layer of material between said reflector and moderator, which prevents substantially the passage of slow neutrons.
The method and apparatus according to the invention is very suitable for the detection of liquid water and/or liquid hydrocarbons present in pipelines for gas transport. The presence of liquid in a gas transport pipeline should be avoided as much as possible because _ . . .. . ... . ..

1(~672~2 the resulting two-phase flow decreases the capacity of the pipeline for gas transport and it is of importance for the operator of the pipeline to be in-formed on the occurrence of two-phase flow in order to enable him to take mea-sures. One source and one detector may be located around the wall of a pipe-line opposite each other for a pipeline with a diameter of less than 10 cm.
Any slug passing this location will be detected~ Still better results are obtained with three sources and three detectors located alternatively around the wall of a pipeline at equal distances. Apart from the detection of the presence of liquid information is obtained on the volume fraction of liquid present at the measuring spot. In the light of the above it is clear that another number of sources and detectors, alternating and equally spaced, will be optimal under certain circumstances.
The invention is very suitable for the detection of the level of a liquid such as a liquid hydrocarbon in a vessel or a column. It is furthermore possible to detect the foam height of such a liquid in a vessel or a column. An interesting application is the detection of the level of a fluid bed of particles of hydrogen containing solid material such as polymeric material.
The detection of levels as indicated above may be used for measurement of the height of a liquid column, a foam or a fluid bed, as well as for alarming and control purposes.
The invention will further be elucidated with reference to the drawings and a number of examples.
Figure l(a) shows schematically a measuring set-up for a detector with a californium-252 source as used in the apparatus according to the invention.
Figure l(b) and l(c) are embodiments of the detection system as used according to the invention.
Figures 2 to 5 show several graphs, representing the measurement-results of the apparatus of the invention.
Furthermore, in every figure the spaces, in which the results were obtained, are represented.

Figure 6 shows a graph, representing another measurement-result.
Figure 7 shows an advantageous embodimen~ according to the invention.
Figures 8 to 11 are graphs, representing the results of several applications of the invention.
Figure l(a) shows, schematically, a measuring set-up for a helium-3 detector 1 with a californium-252 source 2. The detector being pro-vided with a pre-amplifier 3, a high-voltage bias supply 4, an amplifier analyser 5 and a digital rate meter 6.

-6a-_ 1067Z~2 Fig. 1b and c show the detection system, like reference numerals denote like parts, which may be placed in a shielding 7, consisting of a graphite reflector o, a paraffin wax moderator 9 snd a layer 10 of cadmium between the graphite reflector 8 and the paraffin moderator 9. The graphite 8 reflects the neutrons from the source 2 towards the medium (not shown) to be measured. The neutrons which pass through the graphite ô are absorbed by the paraffin wax 9.
To prevent slow neutrons returning from the paraffin wax 9 to the detector 1 a layer 10 of cadmium is provided. This shielding in-creases the background signal at the detector 1, but this increase is more than compensated for by an increase in the signal from the measuring medium. The inclusion of the shielding 7 is thus equivalent to an increase in the source strength.
This shielding thus has two advantages:
1. Reduction of the dose rate by at least a factor of 3.
2. A reduction in background signal variation due to variations in the immediate surroundings. For example, if the shielding is omitted, a person approaching the detector causes a slight increase in the background signal.
This set-up is preferably used in the examples I to V which will now be discussed.
EXAMPLE I
A settler made of 2 cm thick steel, with an outlet at 2.55 m height and with a diameter of 2.00 m was used to separate an alkylate/
propylene mixture from water. The neutron scattering method was used to detect the alkylate-propylene/gas interface for which purpose a probe was used containing 2.5 ~g californium-252 as a neutron source and a helium-3 detector mounted on an aluminium pipe which could be moved along the outer surface of the steel wall. The neutron-scattering intensity is given in counts per second along the horizontal axis as a function of height in meters above the bottom of the settler along the vertical axis in fieure 2. The plotted numbers are net counts beine the difference between observed number of counts and the number of counts (~700 c.p. 10 sec) without any scattering medium present. A strong increase in signal is observed when the probe is moved outside the settler in downward direction. The level found at 2.55 + 0.05 m corresponds exactly with the centre of the alkylate/poly-propylene outlet.
The settler is indicated in figure 2 as 11, with an inlet 12, a bottom outlet 13 for water and an outlet 14 for alkylate/propylene. The height scale in the graph corresponds with the actual height at the settler, EXAMPLE II
Similar measurements as described in example I have been carried out on a flasher of a propane deasphaltine unit in order to detect foam and liquid levels.
In figure 3 the flasher is indicated by 14 and consists of a column of 10 m height and 3 m diameter made of steel. Two trays 15 and 16 are present.
The feed inlet with a tray is indicated by 17. A wire mat 18 is present to pre-vent liquid droplets leaving the column. An outlet 19 for gas is present at the ~Je~iC~
~ 20 top and an outlet for liquid 20 near the bottom. The ~i7-r~-~ axis of the ho~i20~Jt~L/
graph corresponds with the actual height at the flasher in meters, the vcrtical axis corresponds with the counts per 10 seconds.
It is shown in the graph that the liquid level in the column is present at ~l,6 m, The smaller peaks in the counts indicate liquid present on the trays and the feed inlet tray, There is virtually no foam above the feed inlet as is clear from the low counting rate above 7 m height.

,, . , ,, _ ~ _ ~0~7Z~Z
EXAMPLE III
Similar measurements as described in examples I and II have been carried out on an asphalt flasher unit. In figure 4 the flasher is indi-cated by 21 and consists of a column of 7 m height and 2.3 m diameter made of steel. The feed inlet is indicated by 22, A wire mat 23 is present to prevent liquid droplets leaving the column. An outlet 24 for gas is present at the top and an outlet for liquid 25 near the bottom. There are no trays in this flasher. The vertical axis of the graph corresponds with the actual height at the flasher in meters and its horizontal axis with the counts per 10 seconds.
The liquid level is present at 1.1 m as is clear from the sharp increase in counting rate. ~o foam is present above the liquid.

EXAMPLE IV
Similar measurements as described above have been carried out on a flasher for deasphalted oil. In figure 5 the flasher is indicated by 31. It is provided with a feed inlet and tray 32, a gas outlet 33 and an outlet for liquid 34. A wire mat 35 is also present and the graph again shows the relationship between the actual height at the flasher and the counts per 10 seconds like in fig. 4.
This flasher below the feed tray is filled with foam as is clear from the counting rates below a height of 8m. In this flasher no liquid level could be detected because of the presence of a concrete support at the location where the level was expected. The measuring points show a distinct scatter which is probably caused by density fluctuations of the foam.

EXAMPLE V
Measurements have been carried out on a stripper which is used to dry polypropylene powder with nitrogen in order to detect the surface of the fluid bed. The stripper is a steel vessel with ~067Z~Z

a height of 3.9 m and a diameter of 1.6 m. Fluidi~ation of the contents was carried out with 750 kg N2 per hour. ~esults of measurements along a vertical line outside the wall are shown in figure 6, which represents along the vertical axis the height in meters and along its horizontal axis the counts per second, it is clearly shown that a strong signal increase, due to the presence of polypropylene is found if the probe is moved down the reactor wall.
From the examples I to V can be concluded that the gauge, consisting of a californium-252 source and a helium-3 detector, is an effective tool for external detection of hydrocarbon levels in vessels.
Further experiments for testing the neutron gauge as an external level detector were carried out with an artificial hydrocarbon level, which was created behind a steel wall by piling paraffin wax bricks behind various steel plates with thicknesses from 2.5 to 14 mm. The gauge was located on the other side of the steel plate at a fixed position. By removing rows of paraffin wax bricks the level was effectively moved with respect to the gauge. It appeared to be possible to detect levels behind steel walls of up to 14 cm thickness.
Experiments also showed that depending upon the response time of the gauge the source strength may be reduced to only 0.1~ gram for several applications.
It will further be shown that the present method, as well as apparatuses are extremely useful in acquiring a better understanding of two-phase flow phenomena.
In the production and processing of natural gas, the heavier components of the gas tend to form a liquid phase called condensate.
This liquid may be either water or hydrocarbons with five or more carbon atoms in the molecule. The condensate is, in general, transported along with the natural gas until it is removed by gas condensate separators.

lQ67ZlZ

Whilst in the pipeline, however, the condensate affects the transport of the natural gas. A better understanding of two-phase flow phenomena is thus especially important in the design of natural gas transport systèms.
In a bench-scale set-up the detection of hydrogen containing materials with one Cf_252 source and a He-3 detector was studied. F'or this purpose use was made of a piece of 30 cm 3" I.D. gas transport pipe with a steel wall thickness of 15 mm. The ends were closed by two metal prices welded on the pipe. This container was connected to a supp]y of water so as to be able to fill it gradually, while it had an open connection with the atmosphere. The source and detector were located with respect to the pipe diametrically opposite each other. Gamma-ray atte~uation measurements were made on the same pipe. The signals at zero hold-up, i.e. only air in the pipe were normalized to 100%; an increasing hold-up gave an increaseinsignal for the neutron scattering, while an exponential decrease was observed, as expected, for the gamma signals. The gamma-ray absorption only yields information about the liquid hold-up in the optical path of the gamma-ray beam while the neutron scattering gives a signal related to the total amount of liquid present in this pipe, It appeared that the gauge has its lowest sensitivity for small hold-ups. For a hold-up increase from zero to 0.1 a signal increase of 50% is found while from zero to Q.2 liquid fraction, the signaL
increases by 300%.This initial low sensitivity is probably due to the fact that several neutron-proton collisions are needed to sufficiently slow down a neutron and to achieve a substantial increase in detection probability, If only a small amount of hydrocarbon is present the relative probability of more than one collision gets very small.

10~7ZlZ

This low initial sensitivity can be a disadvantage if small hold-ups have to be measured accurately when no other scattering ma-terial such as a high pressure gas-phase is present. To solve this problem polyethylene covers were constructed. The amount of atomic hydrogen (13 g) and the geometry needed to achieve optimal conditions have been determined experimentally. It shall be clear that any material, other than poly-ethylene, which contains hydrogen will be suitable for this purpose.
The location of the liquid phase in a gas transport pipe, with respect to the source and detector will affect the measured sienal. The signal will also be affected by the position of the source with respect to the detector. These dependences are referred to as geometry effects.
In actual gas transport pipelines there is no a priori knowledge of the two-phase flow geometry. This will give a large inaccuracy in the hold-up determination if only one source and one detector are used. In the following a measuring set-up using several sources and detectors is discussed which almost completely eliminates geometry effects.
Fig. 7 shows, schematically, a measuring set-up employing three sources 42 , 42 and 42 and three detectors 43 , 43 and 43 placed alternatingly and symetrically around a pipe 41, which is partly filled with water 44.
The signals of each separate detector will be different, although ll ll l to a lesser extent for the detectors 43 and 43 , however the sum of the signals will be a measure for the quantity of water present.
Experiments showed that for pipe diameters up to 5 an arrangement with three detectors and three sources is within 1% standard deviation independent of geometry effects. Said experiments were carried out by displacing the sources and detectors with respect to the water, as well as by means of three concentric rings of glass tubes, which were placed inside the pipe tnot shown) and could separately be filled with water.

_ .

~06721Z

It was found that there is a well-defined correlation between the sum signal of the three detectors and the l;quid hold-up in a gas transport tube. By calibration a signal can be converted into a hold-up value. It was further possible, by comparing the three separate detector signals, to determine -the location of the liquid present in the pipe.
No scattering due to the gas phase occurred in the experiments which were hereinbefore discussed with respect to pipes. However, in actual gas transport lines, where pressures may be as hieh as 250 bar, the density of the gas phase is su~ficiently high to contribute significantly to the neutron scattering.
To simulate an actual eas transport pipe on a laboratory scale a 15 l. gas cylinder with an I.D. of 14 cm, was pressurized with methane.
Fig. 8 shows the signal increase as a function of gas pressure, in bar along the horizontal axis, indicating that the neutron scattering gauge can also be used as a completely external pressure gauge. It should be noted, however, that the neutron scattering signal is only indirectly related to the gas pressure, the gauge in fact determines the density of hydrogen atoms inside the cylinder.
To simulate the two-phases in natural gas transport lines as closely as possible, the condensate was replaced by water which has about equal hydrogen content, on a volume basis, is easier to h~ndle and has a negligible solubility for methane. The gas phase was methane at 100 bar. In this experiment the detector-covers were not used since the gas phase has sufficient initial hydrogen at zero hold-up.
Fig. 9 shows the sum signal of the three detectors along the horizontal axis versus liquid hold-up in the cylinder, The signal offset of about 5~ is due to neutron scattering in the gas phase, This 10672i2 result indicates that hold-up measurements for two-phase flow can be made on actual gas transport lines. If the gas pipeline is con-siderably larger than 14 cm, I.D. then more than three detectors and sources may be applied.
Time-dependent two-phase flow measurements were made with a pipeline for experimental purposes of 100 m length and 5 cm diameter.
Air was pumped through this pipe together with water in various amounts. Three sources and three detectors were placed around the pipe in an arbitrar,v location, Scattering measurements were carried out as a function of time, It depends very much on the air velocity and the amount of water in which way the water passes through the pipe, The air blows over the surface of the water and causes waves, the magnitude of which varies from ripples to surges, The measure-ments of the three detectors have been added and used to calculate the hold-up of water with the aid of a calibration carried out pre-viously. ~esults are shown in flgure 10 and figure 11, both giving the relationship between volume fraction along the vertical axis and time ln seconds along the horizontal axis, In figure 10 the arrival of water at the measuring location occurred at 1,5x103 sec, The volume fraction of water was virtually constant after 2,5x103 sec.
at a level of 0,33, Small thin waves were visible at more or less regular intervals, In figure 11 the same amount of water was used and a much higher air velocity, Large peaks were detected? almost reachlng through the entire cross-section of the pipe, _ 14 -

Claims (11)

THE EMBODIMENTS OF THE INVENTION IN WHICH AN EXCLUSIVE
PROPERTY OR PRIVILEGE IS CLAIMED ARE DEFINED AS FOLLOWS:
1. Apparatus for detecting an interface of materials having different hydrogen content, present in an enclosed room, provided with at least one neutron source and at least one neutron detector, which is situated at a certain distance from said neutron source, wherein the enclosed room is a metal walled vessel or pipe to be used in process industry, and wherein the neutron source which consists of californium-252 and the detector are located near or at the outerside of the metal wall of the vessel of pipe, said dis-tance between source and detector not being larger than 50 cm, and the detec-tor(s) having a larger sensitivity for scattered neutrons than for neutrons emitted by the source.
2. Apparatus as claimed in Claim 1, wherein the source(s) and the detector(s) are positioned along a circle line near the outside of the metal wall of the vessel or pipe in such a way that the centre of gravity of both are in a plane, which is perpendicular to the centre line of the vessel or pipe.
3. Apparatus as claimed in Claim 1, wherein the source(s) and the detector(s) are positioned behind each other, the source(s) being nearest to the wall.
4. Apparatus as claimed in Claim 1, wherein at least one source and one detector are located around the wall of a pipeline.
5. Apparatus as claimed in Claim 4, wherein three sources and three detectors are located alternatively around the wall of a pipeline at equal distances.
6. Apparatus as claimed in Claim 4, wherein more than one detec-tor is applied, and wherein a device for a comparison between the signals of each of the detectors with each other is present, so as to determine the loca-tion of the liquid in the pipeline for gas transport.
7. Apparatus as claimed in Claim 4, wherein three sources and three detectors are located alternatively around the wall of a pipeline at equal distances and wherein a device for a comparison between the signals of each of the detectors with each other is present, so as to determine the loca-tion of the liquid in the pipeline for gas transport.
8. Apparatus according to Claim 1, wherein a detector is pre-sent, being at least partly enveloped with a cover made of hydrogen contain-ing material.
9. Apparatus according to Claim 11 wherein three sources and three detectors are located alternatively around the wall of a pipeline at equal distances, and a detector is present, being at least partly enveloped with a cover made of hydrogen containing material.
10. Apparatus according to Claim 1, wherein more than one detec-tor is applied, and wherein a device for a comparison between the signals of each of the detectors with each other is present, so as to determine the loca-tion of the liquid in the pipeline for gas transport, and a detector is pre-sent, being at least partly enveloped with a cover made of hydrogen containing material.
11. Apparatus according to Claim 1, wherein three sources and three detectors are located alternatively around the wall of a pipeline at equal distances and wherein a device for a comparison between the signals of each of the detectors with each other is present, so as to determine the loca-tion of the liquid in the pipeline for gas transport, and a detector is pre-sent, being at least partly enveloped with a cover made of hydrogen containing material.
CA256,527A 1975-08-21 1976-07-07 Interface detection by neutron scattering Expired CA1067212A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3477675A GB1548868A (en) 1975-08-21 1975-08-21 Interface detection by neutron scatterng

Publications (1)

Publication Number Publication Date
CA1067212A true CA1067212A (en) 1979-11-27

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ID=10369808

Family Applications (1)

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JP (1) JPS5226886A (en)
CA (1) CA1067212A (en)
CH (1) CH610664A5 (en)
DE (1) DE2637358A1 (en)
FR (1) FR2321684A1 (en)
GB (1) GB1548868A (en)
NL (1) NL7609214A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60250216A (en) * 1984-05-25 1985-12-10 Osaka Gas Co Ltd Discrimination of inside condition of pipe
GB2340229A (en) * 1998-07-28 2000-02-16 British Nuclear Fuels Plc Neutron absorption monitoring
JP2007163352A (en) * 2005-12-15 2007-06-28 Japan Energy Corp Liquid level meter and measuring of liquid level

Also Published As

Publication number Publication date
CH610664A5 (en) 1979-04-30
FR2321684A1 (en) 1977-03-18
FR2321684B1 (en) 1982-04-16
NL7609214A (en) 1977-02-23
DE2637358A1 (en) 1977-03-03
JPS5226886A (en) 1977-02-28
GB1548868A (en) 1979-07-18

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