WO2010133875A1 - Contrôleur de sable - Google Patents

Contrôleur de sable Download PDF

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Publication number
WO2010133875A1
WO2010133875A1 PCT/GB2010/050813 GB2010050813W WO2010133875A1 WO 2010133875 A1 WO2010133875 A1 WO 2010133875A1 GB 2010050813 W GB2010050813 W GB 2010050813W WO 2010133875 A1 WO2010133875 A1 WO 2010133875A1
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WO
WIPO (PCT)
Prior art keywords
vessel
sand
gamma
neutrons
source
Prior art date
Application number
PCT/GB2010/050813
Other languages
English (en)
Inventor
Paul. David Featonby
Peter Jackson
Kenneth James
Thomas John Partington
Original Assignee
Johnson Matthey Plc
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Johnson Matthey Plc filed Critical Johnson Matthey Plc
Publication of WO2010133875A1 publication Critical patent/WO2010133875A1/fr

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Classifications

    • 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
    • G01N2223/10—Different kinds of radiation or particles
    • G01N2223/106—Different kinds of radiation or particles neutrons
    • 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

Definitions

  • the present invention concerns a method for determining the presence of a particular material, especially sand, in a vessel and an apparatus for use in such a method.
  • the apparatus for measuring the amount of sand or scale contained within a vessel containing one or more fluid phases, using the method of the invention, the apparatus comprising: a. a source of neutrons; b. a detector suitable for detecting high energy gamma emitted from at least one element known to be present in the sand or scale and generating a signal in response thereto; and c. means for calculating, from the signal generated by the detector, the amount of said sand or scale within the vessel.
  • the fluid comprises an aqueous and/or hydrocarbon fluid flowing within a pipeline. More preferably the fluid comprises at least a portion of the fluid produced from an oil and/or gas production well.
  • Prompt gamma neutron activated analysis is a method of detecting the presence of one or more chemical elements by the characteristic emission of prompt gamma radiation when thermal neutrons are captured by nuclei of the element. Near instantaneous gamma photon emissions can also occur through higher energy neutrons colliding inelastically with the target element. The inelastic collision may cause excitation of the nucleus resulting in the release of energy in the form of gamma photons of a characteristic energy resulting in the stabilisation of the nucleus. The gamma photons may be detected and their energy levels measured. The number of photons, i.e.
  • the target material may be any which contains an element (the "target element") susceptible to produce prompt gamma emission when its nucleus interacts with a neutron and which is identifiable from the energy of such prompt gamma radiation. Prompt-gamma photons emitted from more than one target element may be measured.
  • the ratio of elements may be indicated by the ratio of the intensity of the characteristic peaks of the elements and such ratios may be used to assist in identifying the target material. Where a single element is to be identified, it too may exhibit a characteristic relationship between the intensities of prompt-gamma peaks of different energies, which may be used to identify the element of interest from the energy spectrum.
  • Aluminium-28 has a half-life of approximately two minutes when activated in this manner, which makes down-stream detection possible.
  • the ability to detect the activated sand downstream is beneficial as the gamma photon detection system is located away from the source and thus does not detect gamma photons from neutron interactions with other elements positioned close to the source.
  • the high level of counts due to prompt gammas from hydrogen and other elements in the process media or pipe walls may cause problems for detection systems located close to the neutron source.
  • the gamma radiation detected in the method and by the apparatus of the invention may be prompt gamma emission, delayed gamma emission or both prompt and delayed gamma emission.
  • the prompt gamma emission may be caused by capture of thermal neutrons by a nucleus of the target element or by inelastic scattering of fast neutrons as they interact with the target element nuclei.
  • the gamma radiation caused by different types of neutron-nucleus interaction have different characteristic energies for each type of element.
  • the target material is sand and the target element for which gamma emission is sought is preferably silicon, although other emission energies characteristic of other elements, such as aluminium, may be monitored in addition to or instead of the silicon energies.
  • the amount of silicon present in the part of the contents of vessel measured is used to calculate the amount of sand in that part of the vessel. Using measurements made at different times, this calculation may be used or extended to calculate time-dependent properties such as monitoring whether the amount of sand in a part of a vessel changes over a period of time, or monitoring how sand flows along a pipeline or through process apparatus, using the calculated amount of sand at different locations in a vessel, pipeline or process apparatus as appropriate.
  • the method and apparatus may have other applications, for example to detect elements associated with the formation of scale within a tank or pipeline.
  • characteristic prompt and/or delayed gamma emission of appropriate elements known to be present in the scales to be measured are measured by the detector(s) and used to calculate the amount of the particular scale of interest.
  • Scales vary in composition and so the elements selected for monitoring also vary according to the application. Suitable elements found in oil-field scales include Ba, Fe, Mg, Ca and Sr. Measurement of scale formation may be useful in a decision whether to deploy scale removal operations or to adjust certain process measurements to account for the presence of scale.
  • the fluid When the method is used for monitoring sand or scale produced in an oil and/or gas well, the fluid usually comprises at least one continuous phase of oil, water, gas and discontinuous phases such as emulsions and foam. Frequently the fluid comprises more than one of these materials.
  • a hydrogen-rich fluid such as a hydrocarbon fluid or water, provides a medium in which fast neutrons, which are capable of passing though a vessel wall, are slowed or moderated to become "thermal neutrons" which may be captured through inelastic collision with the nuclei of materials within the vessel. This makes the use of PGNAA using an isotope source of neutrons especially suitable for the detection of sand in a hydrocarbon and/or water flow.
  • the vessel may be a container such as a tank, drum, pressurised storage container, separator or other process vessel; or it may be a pipeline though which the fluid may flow.
  • the vessel wall may be relatively thick when used to contain or transport fluids under pressure.
  • the method is especially useful for in-line, real-time monitoring, e.g. as fluid flows through a pipeline, because the prompt-gamma emission is immediate upon excitation of a target nucleus by inelastic collision with a thermal neutron and may produce little residual emission when irradiation with neutrons has ceased.
  • the neutron source is selected from suitable available neutron sources such as neutron generators and radioisotope sources. The selection of an appropriate neutron source should be made according to the situation and application for which the method is applied.
  • neutron generators Whilst neutron generators may be appropriate to be used in some applications of the method, they tend to be relatively expensive and bulky so may be less practical to use in a compact instrument.
  • the preferred type of neutron source is an isotope source such as californium ( 252 Cf) or americium/beryllium ( 241 Am/Be) which tends to be cheaper and has a longer half-life.
  • isotope sources emit fast neutrons and, if PGNAA is to be employed, these must be slowed to produce thermal neutrons using a moderator which is usually a hydrogen-rich material.
  • a hydrocarbon and water containing fluid within the vessel itself is capable of moderating the fast neutrons
  • variations in the amount and composition of such fluid may produce variations in the number of thermal neutrons available to interact with the target material. Such variation is likely to affect the accuracy of the measurement due to fluctuations in the intensity of the prompt gamma emission peak.
  • a moderator material between the source and the vessel wall in order to moderate the neutrons before they enter the vessel.
  • Suitable materials are known and include hydrogen-rich materials, especially hydrogen- rich polymers such as polyethylene. Moderation of the neutrons before they enter the vessel also has the advantage that the probability of producing long-term activation of the vessel walls is reduced.
  • the intensity of the hydrogen peak is monitored in order to estimate the degree of thermalisation occurring due to hydrogenous material in the fluid contained in the vessel. This information may then be used to compensate the measured signal intensity for the measured level of thermalisation.
  • the moderator when activation of the target element by both thermal neutrons and fast neutrons is required then the moderator, if provided, may be shaped so that only a portion of the neutrons generated or emitted by the source pass through the moderator before entering the vessel, the moderator may be shaped to include holes through which fast neutrons may pass or the moderator may be shaped and/ or located such that only neutrons emitted from a portion of the source are moderated. Alternatively, more than one source may be provided and in such a case, none, some or all of the sources may be moderated.
  • DNAA is to be employed it is beneficial for high-energy neutron sources to be used.
  • Deuterium- tritium neutron generators emit neutrons of 14.4MeV, which are of particular use in producing the silicon n,p reaction
  • the neutron source should be appropriately shielded and collimated to emit neutrons towards and into the vessel whilst protecting the surrounding environment, personnel and equipment from neutron bombardment.
  • the neutron source may be located outside the vessel adjacent or near-adjacent (allowing for the presence of a moderator) the vessel wall. In some cases it may be desirable to locate the neutron source within a dip-tube of neutron-permeable material and install the dip-tube at a desired location within a vessel. Such an arrangement may be beneficial when the vessel is very large or when the contents are likely to vary within the vessel. More than one neutron source may be provided for use in the method. The use of multiple neutron sources may be advantageous, as the volume of fluid contents irradiated may thereby be increased, thus increasing sensitivity.
  • the shielding and collimation of the neutron source(s) should be provided as appropriate to the location of the source.
  • the handling of radioisotopes and neutron generators must always be carried out with care by suitably trained personnel with due regard to the necessary licences and procedures.
  • the gamma radiation emitted from the vessel is detected using an energy-sensitive gamma detector. It is desirable to employ detectors with large sensing elements so that high-energy gamma photons are detected and also to increase the sensitivity of the instrument. The sensitivity of the instrument may also be increased by using more than one detector. Suitable types of detector include scintillation detectors, including, for example, sodium iodide or lanthanum bromide detectors, and semiconductor detectors, for example a germanium detector.
  • the detector(s) may be located outside the vessel in a position selected to detect the emitted gamma photons, close to the vessel. Alternatively the detector may be located within the vessel, optionally within a dip-tube of radiation-permeable material.
  • Location of the detector within a dip-tube provides a protected environment for the detector, whilst allowing more flexibility in selecting its preferred location.
  • Power sources and other equipment for operating the detector(s) such as a photomultiplier, control means, communication means (cables, wireless transmission/reception means) etc are provided by known methods for radiation detectors.
  • the detector is shielded from detecting directly the neutrons generated by the source and from other sources of gamma radiation.
  • the detector may be positioned on or near a portion of the vessel which is opposite the position of the neutron source or in another position to detect back-scattered photons. More than one detector may be provided.
  • the use of several detectors positioned at locations around the vessel, for example positioned around a particular portion of the vessel of interest, ensures detection of more gamma photons than may be possible by detecting at a single location and this is beneficial to increase the sensitivity of the method and apparatus.
  • a plurality of detectors may be provided in a housing or sleeve which is adapted to be positioned around at least a part of a vessel such that each detector is positioned in a predetermined position relative to the wall of the vessel.
  • One or more of the detectors may be shaped to conform to the surface of the vessel.
  • a plastic scintillation detector may be moulded to form a shape suitable for detecting prompt gamma radiation around at least a portion of the circumference of a vessel, in particular a pipe.
  • one or more detectors may be located remote from, e.g. downstream, of the neutron source.
  • the position of the neutron source and detector may need to be selected to provide the required information, e.g. the amount of material in the settled mass or within a flowing fluid.
  • the detection of stationary masses within a pipe containing a flowing fluid may be achieved using one or more conventional flow meters such as an ultrasonic flow meter.
  • the instrument should be positioned to minimise attenuation of the neutrons or emitted gamma radiation.
  • the detector detects an energy spectrum.
  • the gamma radiation emitted over a range of energies including the characteristic gamma peak emission energy due to neutron activation of at least one element known to be present in the target material should be monitored.
  • the output from the detector may be filtered to contain only portion(s) of the energy spectrum known to contain the gamma peak(s) characteristic of the target material.
  • it is usually the silicon or aluminium peak energies which are of interest.
  • High cross-section silicon prompt gamma peaks from thermal neutron capture, such as 3538 keV, 5 MeV and other energies, are useful characteristic peaks for detecting sand. These peaks have high cross-section at about 0.1 barns.
  • the actual peak selected for silicon detection may depend upon the energies of radiation emitted by the presence of other elements that are also activated by the neutrons.
  • the thermal capture of neutrons in iron (in the vessel wall) produces many characteristic energies, many of which are around 3.5 MeV and 5 MeV and may make the silicon peaks with the largest cross-sections difficult to resolve.
  • a higher energy silicon peak such as the one at 8.45 MeV, may be preferred, even though it has a much lower cross-section (0.004 barns).
  • the choice of which prompt silicon characteristic energies to measure and use in the calculation of the amount of silicon present may also be dependent on the resolution capabilities of the detector used.
  • delayed gamma emission When delayed gamma emission is to be detected, it is preferred to measure the peak occurring at an energy of about 1.78 MeV.
  • This characteristic energy is emitted from aluminium-28 formed when silicon-28 is activated by the capture of a fast neutron.
  • Prompt gamma emission from inelastic neutron scattering (INS) from silicon also has a useful characteristic energy peak at 1.78 MeV.
  • thermal neutron capture by aluminium- 27 can produce aluminium-28 which is the same isotope (producing the same 1.78 MeV photons) producing delayed gamma emission by the capture of a fast neutron by a silicon atom.
  • Knowledge of aluminium:silicon ratios in the sand to be detected may be required in order to distinguish the photons emitted following interaction of neutrons with Si from those emitted following interaction of neutrons with Al. Calculation of Si content from other detected emissions, especially the prompt gamma emissions, may facilitate identification of Al prompt gamma emissions.
  • a sand monitor according to the invention preferably measures counts occurring within one or more energy windows containing the selected silicon peak or peaks.
  • the gamma radiation emitted from the vessel is detected over a range of energies including at least one characteristic prompt or delayed gamma emission energy peak at about 3.5 MeV, about 5 MeV, about 8.45 MeV and/or about 1.78 MeV.
  • a characteristic prompt or delayed gamma emission energy peak at about 3.5 MeV, about 5 MeV, about 8.45 MeV and/or about 1.78 MeV.
  • the measured energy level peak at about 3.5 MeV may vary slightly from 3.5 MeV but nevertheless be identifiable as a characteristic prompt gamma emission from silicon.
  • the detector(s) may be calibrated using isotopes of known energy. Once installed the calibration may be confirmed through identification of the hydrogen prompt gamma peak.
  • the hydrogen prompt gamma peak at 2.23 MeV is readily detectable due to the high cross-section of hydrogen, the abundance of hydrogen in the process media and because only a single peak is produced.
  • the position of the hydrogen peak may be tracked during instrument operation to monitor any drift in energy measurements due to factors such as changes in environmental conditions. If any drift in energy measurements is identified, a compensation function may be applied to compensate for the effect, e.g. of temperature, on the gamma detection system.
  • the intensity of the hydrogen peak may be monitored and used as means of producing crude liquid cut measurements in an oilfield application.
  • Some of the water / oil contribution to the gamma energies measured may be eliminated through calibration or prior knowledge of the carbon and oxygen prompt energies.
  • a measure of process media bulk density (using known gamma transmission methods) and hence liquid cut may be of use when compensating for carbon and oxygen contribution.
  • carbon and oxygen have minimal prompt contribution and compensation may not be required.
  • the sand monitor instrument is preferably also calibrated to establish the correlation between silicon gamma intensity, i.e. the number of gamma photons detected at one or more characteristic energy levels, and sand content of the vessel.
  • the neutrons impinging on the vessel wall may activate the wall material to produce prompt, or even delayed, gamma emissions.
  • the gamma radiation emitted from the vessel wall should not be allowed to interfere with the prompt gamma emissions measured in order to determine the amount of the target material.
  • One method of achieving this is to measure the prompt gamma emitted by the wall material, for example by performing calibration measurements on a sample of the vessel wall (such as an equivalent pipe) and then subtracting the energy spectrum produced by the vessel wall from the energy spectra produced during the measurement of the target material, for example by using appropriate known spectrum subtraction algorithms in the data processing unit. When only a portion of the energy spectrum is processed, i.e.
  • the location of a gamma radiation detector at a position remote from the part of the vessel in the path of the neutrons emitted from the source may alleviate this problem. This is particularly suitable for the detection of sand or other elements flowing in a fluid within the vessel. In this way the gamma radiation emitted from the target material can be detected by a detector located downstream (in the direction of fluid flow) of the neutron source so that emission from the vessel wall is not detected. This is a particular benefit of measuring delayed gamma emission from the fluid, in that the gamma radiation may be emitted for sufficient duration for the target material to have flowed away from the location of the neutron source and be detected downstream of the neutron source.
  • Elements may occur within the vessel material, the fluid, the target material or another material which is present in the vessel that have peaks close to the major characteristic peaks of the selected element of the target material.
  • Test spectra should be examined to identify evidence of the presence of these interfering elements. This evidence may take the form of the prompt or delayed gamma peaks characteristic of the other element identified at energies at parts of the energy spectrum remote from the target element peaks of interest. If interfering elements are found that are known to have peaks close to the energy peaks of interest then compensation may then be applied to the measured peaks. The use of high resolution energy detectors may reduce uncertainty due to neighbouring peaks.
  • Another cause of uncertainty in measuring the target element characteristic peaks of interest is the detection of photons which were emitted at a higher energy but which then interacted with material and have a reduced energy that coincides with that of the target element peaks of interest.
  • This problem may be reduced by identifying the presence of higher energy peaks, assessing the probability of interaction with process media and vessel / instrument materials and then predicting the level of lower energy photons produced. This prediction may then be used to apply compensation to the target element peak energies.
  • the use of peaks at higher energies to identify and characterise the target element also reduces the potential for this inaccuracy due to this effect.
  • the sensitivity of the method may be further improved by increasing the counting period of the detectors, i.e. the period of time over which the number of photons of each energy is counted.
  • a Compton shield detector may be provided adjacent the primary detector to detect scattered photons.
  • the number of photons detected by the primary detector may therefore be adjusted to remove scattered photons detected by the Compton shield detector and thereby improve the accuracy of the count of detected photons.
  • the calculation of the amount of sand present from the signal generated by the detector(s) is preferably carried out in a data processing unit.
  • the data processing unit may be located near the vessel or may be located remotely, depending on the ambient conditions and operational requirements of the particular application.
  • the control of the detectors, the signal processing, e.g. data smoothing, and calculations such as spectrum subtraction, peak resolution, peak ratio calculation etc is carried out using known methods and algorithms.
  • the data may be output in the form of an energy spectrum so that the elemental composition may be analysed.
  • the data handling program may be programmed to calculate the amount of sand in the vessel from the energy levels which can be identified and attributed to silicon and then to output the answer as a number or show it on a visual display.
  • the apparatus may be adapted to provide an alarm when the amount of sand changes by a predetermined amount or when it reaches a certain level.
  • Figure 1 a schematic longitudinal section through a pipeline and apparatus according to the invention.
  • Figure 2 a plot of intensity (arbitrary units) vs energy level (keV) for detected prompt gamma emission from a vessel containing water and sand.
  • Figure 1 shows, schematically, a section of a pipeline 10 through which a multiphase fluid 12, comprising water, oil and some sand particles, flows in the direction of the arrow.
  • a neutron generating isotope source comprising 241 Am/Be is contained within shielding 14 which is shaped to provide emission of fast neutrons in the direction of the pipeline.
  • a block of a resilient hydrogen-rich polymer 16 is positioned between the neutron source and the pipeline and serves to moderate the fast neutrons generated by the isotopic source.
  • Gamma detectors 18 and 20 are located to detect gamma energy and generate an energy spectrum.
  • a controller / data processor (not shown in Fig 1 ) is connected to the detectors to control the signal and data processing function.
  • the downstream detector 20 may be configured to detect a delayed gamma emission energy.
  • neutrons generated by the source are emitted towards the pipeline and are moderated to thermal speeds as they pass through the moderating material 16.
  • the neutrons pass through the wall of the pipeline 10 and may interact with matter through inelastic collision with nuclei.
  • Each elemental nucleus capturing a thermal neutron may emit a prompt-gamma photon of an energy which is characteristic of the identity of the element.
  • the detection of a gamma photon characteristic of silicon is indicative of the presence of sand within the pipeline.
  • the detectors count the number of photons detected and the energy level of each photon during a predetermined time period, (the counting period).
  • the amount of sand detected within a counting period may be estimated from the number of photons counted by the detector having an energy level characteristic of the silicon nucleus, i.e. the intensity or size of the energy peak at that characteristic energy level.

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  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Immunology (AREA)
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  • Analysing Materials By The Use Of Radiation (AREA)

Abstract

L'invention porte sur un procédé destiné à la mesure de la quantité de sable ou de tartre dans un récipient. Le procédé comprend la mise en place d'une source de neutrons, amenant au moins quelques uns des neutrons produits par ladite source à entrer en interaction avec le contenu de récipient, et la détection du rayonnement gamma émis par le récipient dans une plage d'énergies comprenant l'énergie d'émission de crête de rayons gammas instantanés ou retardés d'au moins un élément cible que l'on sait être présent dans le sable. L'invention porte aussi sur un appareil destiné à être utilisé dans le procédé de l'invention. Le procédé et l'appareil sont particulièrement utiles dans l'industrie de récupération de l'huile et du gaz, pour détecter le sable ou la formation de tartres dans une canalisation.
PCT/GB2010/050813 2009-05-19 2010-05-18 Contrôleur de sable WO2010133875A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB0908534A GB0908534D0 (en) 2009-05-19 2009-05-19 Sand monitor
GB0908534.1 2009-05-19

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Publication Number Publication Date
WO2010133875A1 true WO2010133875A1 (fr) 2010-11-25

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WO (1) WO2010133875A1 (fr)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2015019170A1 (fr) * 2013-08-09 2015-02-12 Vetco Gray Scandinavia As Procédé et dispositif pour la détection de matériau déposé
US9995725B2 (en) 2016-06-28 2018-06-12 Schlumberger Technology Corporation Phase fraction measurement using light source adjusted in discrete steps
US10054537B2 (en) 2016-06-28 2018-08-21 Schlumberger Technology Corporation Phase fraction measurement using continuously adjusted light source
CN109541670A (zh) * 2018-11-19 2019-03-29 西北核技术研究所 散裂中子源1MeV等效中子注量的测量方法

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
DIBBS H P ET AL: "DETERMINATION OF THE COMPOSITION OF SLURRIES BY THE MEASUREMENT OF THERMAL-NEUTRON-CAPTURE GAMMA RADIATION", REPRINT SERIES. MINES BRANCH. DEPARTMENT OF MINES AND TECHNICAL SURVEYS,, 1 January 1972 (1972-01-01), pages 1 - 24, XP009136779 *
DUFFEY D ET AL: "Analysis of geothermal power plant water using gamma rays from capture of californium 252 neutrons", NUCLEAR TECHNOLOGY, AMERICAN NUCLEAR SOCIETY, CHICAGO, IL, US, vol. 27, no. 3, 1 November 1975 (1975-11-01), pages 488 - 499, XP009136816, ISSN: 0029-5450 *
WOODBURY FRANKLIN B W: "APPLICATION OF THERMAL NEUTRON CAPTURE-GAMMA RAY ANALYSIS TO OXIDIZED TACONITE BENEFICIATION PROCESS SLURRIES", REPORT OF INVESTIGATIONS, UNITED STATES BUREAU OF MINES, US, no. 8460, 1 January 1980 (1980-01-01), pages 1 - 71, XP009136764, ISSN: 0096-1922 *

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2015019170A1 (fr) * 2013-08-09 2015-02-12 Vetco Gray Scandinavia As Procédé et dispositif pour la détection de matériau déposé
US9995725B2 (en) 2016-06-28 2018-06-12 Schlumberger Technology Corporation Phase fraction measurement using light source adjusted in discrete steps
US10054537B2 (en) 2016-06-28 2018-08-21 Schlumberger Technology Corporation Phase fraction measurement using continuously adjusted light source
CN109541670A (zh) * 2018-11-19 2019-03-29 西北核技术研究所 散裂中子源1MeV等效中子注量的测量方法

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