CN109298440B - Using method of fixing support for radioactivity measurement - Google Patents
Using method of fixing support for radioactivity measurement Download PDFInfo
- Publication number
- CN109298440B CN109298440B CN201811351807.4A CN201811351807A CN109298440B CN 109298440 B CN109298440 B CN 109298440B CN 201811351807 A CN201811351807 A CN 201811351807A CN 109298440 B CN109298440 B CN 109298440B
- Authority
- CN
- China
- Prior art keywords
- pipe body
- sample
- cover plate
- probe
- cylindrical
- 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.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
Landscapes
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention relates to a use method of a fixed support for radioactivity measurement, wherein the outline of the support is of a cup-shaped structure, a cylindrical cup wall is formed by a pipe body and a limiting part, and a cover plate is connected with the pipe body, wherein the use method at least comprises the following steps: sleeving the pipe body outside the probe of the detector, so that the end face of the pipe body, which is far away from the cover plate, is contacted with the end face of the probe end of the electronic part; make spacing portion and the preceding terminal surface contact of refrigeration portion through adjusting spacing portion to continue to remove spacing portion along the direction of detector, make the support remove along the direction that deviates from the detector, its displacement reads out through being located scale on the body outer wall. The invention realizes the function of accurately adjusting the relative position of the sample to be measured and the probe of the detector, and can meet more requirements of accurate efficiency scales and the like of tightly combining different media and different positions with actual measurement in the radioactivity measurement process.
Description
The invention discloses a split application of a fixing bracket for rapidly measuring an environmental sample on site, which is applied for 201610948413.1 on 2016, 10 and 26 days and is of the application type.
Technical Field
The invention relates to the technical field of using methods of measuring and analyzing instruments, in particular to a using method of a fixed support for radioactivity measurement.
Background
With the rapid development of nuclear and radiation technology, nuclear accidents occur more and more, especially, explosion of japanese islands and langazar atomic bombs, susan-chernobiles nuclear accidents, japanese fukushima nuclear accidents, etc., resulting in release of a large amount of radioactive nuclides into the environment, and some artificial radioactive substances are distributed throughout the global environment through the way of atmospheric circulation, etc., so that the harm of radioactive substances in the environment to human beings is attracting more and more attention.
The gamma energy spectrum measurement is one of the most mature nuclear analysis methods, and at present, besides the ground application, the gamma energy spectrum measurement technology can be applied to aviation measurement and underground measurement, so that the aviation gamma energy spectrum measurement technology and the gamma energy spectrum logging technology are formed. Since gamma rays contain important information of characteristic nuclides, the technique of energy spectrum measurement of gamma rays is one of the important tasks of nuclear radiation detection. In nuclear physics research, gamma ray measurement is not always necessary, such as measurement of nuclear excitation level, study of nuclear decay scheme, measurement of short nuclear life, and nuclear reaction experiment.
In the radioactivity analysis, for example, the radioactive analysis of ores, the determination of the fuel consumption of fuel elements in a stack, the natural radioactivity analysis of building materials, the neutron activation analysis, and the like are based on the measurement of gamma ray exposure rate and energy. Gamma radiation is also frequently used and various measurements of gamma radiation exposure rates and energies are required in various applications of industrial, agricultural, medical and scientific research of radioisotopes. In the actual measurement, the gamma-ray exposure rate is actually measured by measuring gamma-rays of a specific energy or gamma-ray exposure rates in a specific energy interval.
The gamma energy spectrum method is the most common method for measuring the content of radioactive substances in the environment, and has the main advantages that the sample does not need to be subjected to complex treatment, the content of the radioactive substances in the environmental sample can be directly measured by using a laboratory gamma energy spectrometer, and the activity concentration of the radioactive nuclide in the environmental sample is calculated according to a standard efficiency calibration curve.
The defects of the prior art are as follows: at present, the method for measuring environmental samples mainly comprises the steps of collecting samples back to a laboratory, then carrying out sample pretreatment and other processes, and finally carrying out sample loading measurement, and no mature and accurate standard of a field rapid gamma energy spectrum analysis method exists, so that the method cannot well meet the requirement of carrying out rapid, accurate and high-sensitivity quantitative analysis on various environmental samples collected on the field.
Or in situ measurement of environmental samplesWhen the radioactive nuclide is used, a sample is firstly put into a cylindrical sample box and placed on the surface of a detector for measurement, then gamma energy spectrum analysis is carried out on the environmental sample, and finally the content of the radioactive nuclide in the environmental sample is calculated. However, the beryllium window of the wide-energy detector probe is extremely thin at present, and the thickness of the beryllium window is 10 at most-4m, the probe head of the detector is easily damaged in the measuring process. More importantly, the field gamma energy spectrum is not provided with a bracket for fixing a sample, and the repeatability of each measurement position cannot be ensured, so that the measurement error or uncertainty is greatly increased.
Therefore, the invention designs a bracket special for measuring an environmental sample based on a cylindrical sample box, and the support effect of the side wall of a lead chamber or a probe is used for assisting a detector to carry out on-site accurate measurement on the radioactivity of the environmental sample.
Disclosure of Invention
Aiming at the defects of the prior art, the invention provides a fixed bracket for rapidly measuring an environmental sample on site, which at least comprises: the support is of a cup-shaped structure, a cylindrical cup wall is formed by the pipe body and the limiting part, and a cup seat is formed by the cover plate and the pull rod;
the pipe body is sleeved outside a probe of the detector, the end face, far away from the cover plate, of the pipe body is in contact with the end face of the probe end of the electronic part, the limiting part is made to be in contact with the front end face of the refrigerating part by adjusting the limiting part, the limiting part continues to move in the direction of the detector, the bracket moves in the direction far away from the detector, and the moving distance of the bracket is read through a scale on the outer wall of the pipe body;
the pipe body is at least a double-structure layer formed by an organic glass layer and a tungsten alloy layer, the organic glass layer is sleeved outside the tungsten alloy layer, the outer wall of the organic glass layer is provided with a scale along the axial direction of the pipe body, and the limiting part is sleeved on the outer wall of the pipe body;
the thickness of the organic glass layer of the tube body is increased along the direction far away from the cover plate, the thickness of the tungsten alloy layer is reduced, the sections of the organic glass layer and the tungsten alloy layer along the axial direction of the tube body are right-angled triangles and/or right-angled trapezoids, the contact surface of the organic glass layer and the tungsten alloy layer is a conical surface, and the organic glass layer and the tungsten alloy layer jointly form a cylindrical tube body;
the included angle between the contact conical surface of the organic glass layer and the tungsten alloy layer and the central line of the tube body in the axial direction is 30-90 degrees, and the distance between the edge of the cylindrical groove arranged on the bottom plate and the inner wall of the tube body is greater than the maximum thickness of the tungsten alloy layer.
According to a preferred embodiment, the tungsten alloy layer in the pipe body is in occlusion connection with the organic glass layer through threads, wherein the thickness of the tungsten alloy layer is 0-6 mm; the outer wall of the pipe body is provided with a scale along the axial direction, and the zero point of the scale is located at a port close to one end of the cover plate.
According to a preferred embodiment, the depth value of the sample groove formed by the tube body is greater than or equal to the sum of the length value of the probe and the height value of the sample box for containing the environmental sample, the diameter of the tube body is slightly greater than the diameter of the probe, and the difference is 0.5-1 mm.
According to a preferred embodiment, the length of the position-limiting part is smaller than the length of the probe, and the length of the position-limiting part is larger than the thickness of the electronics part.
According to a preferred embodiment, the central axis of the pipe body is perpendicular to the cover plate, the limiting portion is of a cylindrical tubular structure, the outer wall of the pipe body is provided with external threads, the inner wall of the limiting portion is provided with internal threads, the limiting portion is sleeved on the outer wall of the pipe body based on a thread engagement relation, the central axis of the limiting portion is coincident with the central axis of the pipe body, and the central axis of the limiting portion is perpendicular to the cover plate.
According to a preferred embodiment, the bottom plate is located in the tube body, the bottom plate is of a disc-shaped structure, and the bottom plate and the tube body form a sample groove together;
the end face, facing the sample groove, of the bottom plate is provided with at least one stage of stepped cylindrical groove, the diameter of the groove is smaller as the groove is closer to the cover plate, the different diameters of the stepped grooves of different stages correspond to the diameter of a sample box for containing a radioactive sample to be detected, and the bottom plate is made of at least one of organic glass or tungsten alloy;
the bottom plate disc central axis coincides with the pipe body central axis, and the bottom plate is rigidly connected with the pipe body and the cover plate.
According to a preferred embodiment, the pull rod is of a cylindrical structure, the pull rod is connected with the second end face of the cover plate, and the pull rod is coaxial with the cover plate.
According to a preferred embodiment, the tie rod is provided with an annular groove having a square cross-section in the radial direction of the tie rod.
According to a preferred embodiment, the tie rod is provided with at least one annular groove having a rectangular cross-section in the radial direction of the tie rod.
According to a preferred embodiment, the depth value of the sample groove formed by the tube body is greater than or equal to the sum of the length value of the probe and the height value of the sample box for containing the environmental sample, the diameter of the tube body is slightly greater than the diameter of the probe, and the difference is 0.5-1 mm;
the bottom plate is located in the tube body, the bottom plate is of a disc-shaped structure, the bottom plate and the tube body jointly form a sample tank, the end face, facing the sample tank, of the bottom plate is provided with at least one stage of stepped cylindrical grooves, the diameter of each step of the groove is smaller as the groove is closer to the cover plate, the different diameters of the different stages of the stepped grooves correspond to the diameter of a sample box used for containing a radioactive sample to be detected, and the bottom plate is made of at least one of organic glass or tungsten alloy;
the limiting part is of a cylindrical tubular structure, wherein the outer wall of the pipe body is provided with external threads, the inner wall of the limiting part is provided with internal threads, the limiting part is sleeved on the outer wall of the pipe body based on a thread engagement relation, the central axis of the limiting part is overlapped with the central axis of the pipe body, the central axis of the limiting part is perpendicular to the cover plate, the length value of the limiting part is smaller than that of the probe, and the length value of the limiting part is larger than that of the electronics part;
the cover plate is of a cylindrical disc structure, the disc end face of the cover plate comprises a first end face and a second end face, the first end face is connected with the pipe body and the bottom plate, the second end face is connected with the pull rod, and the cover plate is coaxial with the pipe body, the bottom plate and the limiting part;
the pull rod is of a cylindrical structure, the pull rod is connected with the second end face of the cover plate, the pull rod is coaxial with the cover plate, and at least one annular groove with a rectangular cross section in the radial direction of the pull rod is formed in the pull rod.
The invention has the following advantages:
(1) the fixing support for rapidly measuring the environmental sample on site has the tungsten alloy layer structure of the tube body, so that the influence of natural radioactive substances or natural background in the surrounding environment on measurement in the process of on-site measurement is effectively shielded, and meanwhile, the tungsten alloy layer material also plays a role in shielding the radioactive sample to be measured, and the radioactive damage to measuring personnel is avoided. Simultaneously, the function of accurately adjusting the relative position of the sample to be measured and the probe of the detector is realized through the scale positioned on the outer side of the tube body, and more requirements such as efficiency scale coefficients directly related to actual measurement requirements with extremely high position requirements in the radioactive measurement process can be met.
(2) The fixing support can be used for maintaining the relative measurement positions of the detector and a sample to be measured unchanged in the measurement process, so that the sample and the detector are ensured to be on the same axis, and the repeatability of the geometric positions of the sample and the detector is ensured to be consistent when the sample is placed every time. The problem that the consistency of the geometric conditions of the sample measurement cannot be ensured in the repeated measurement process is avoided. And the problem that in the measurement process of different workers, due to the reasons of non-standard operation, personnel factors and the like, the uncertain factors artificially introduced are large, and therefore large errors are finally brought to the measurement results is solved.
(3) The fixing support for rapidly measuring the environmental sample on site is used for containing the environmental sample to be measured and avoiding the damage to a probe of a detector caused by the direct contact of the sample and the detector.
Drawings
FIG. 1 is a cross-sectional view of a mounting bracket for rapid measurement of environmental samples in accordance with the present invention;
fig. 2 is a schematic structural diagram of the fitting relationship between the fixing bracket and the detector for rapid measurement of the environmental sample according to the present invention.
List of reference numerals
1: a pipe body 2: bottom plate 3: limiting part
4: and (4) cover plate 5: the pull rod 6: groove
7: sample tank 8: the detector 9: front end face of refrigerating part
10: the electronics section 11: the probe 12: beryllium window
Detailed Description
The following detailed description is made with reference to the accompanying drawings and examples.
Fig. 1 shows a cross-sectional view of a fast measuring environmental sample holding rack of the present invention, the rack comprising: the device comprises a pipe body 1 for containing radioactive environment samples, a bottom plate 2 for supporting the samples, a limiting part 3 for determining the relative position of the support and a measuring instrument, a cover plate 4 for supporting and fixing the pipe body 1, the bottom plate 2 and the limiting part 3, and a pull rod 5 for moving the support. The support profile is cup-shaped structure, has constituted cylindrical cup wall by body 1 and spacing portion 3, constitutes the cup seat by bottom plate 2, apron 3 and pull rod 5. The radioactive environmental sample to be tested is placed in the tube body 1 and in the sample groove 7. The probe of the radioactive detector is coaxial with the central axis of the tube body, and the probe is opposite to the sample groove 7.
The pipe body 1 in the support structure is a cylindrical pipe body. The pipe body 1 is rigidly connected with the cover plate 4. The central axis of the pipe body is perpendicular to the cover plate 4. According to a preferred embodiment, the cover plate 4 is provided with a circular groove, the inner wall of the groove is provided with internal threads, the outer wall of the pipe body 1 close to the cover plate 4 is provided with external threads, and the pipe body 1 is connected with the cover plate 4 through a thread meshing relationship. The tube body 1 is made of organic glass, tungsten alloy or organic glass and tungsten alloy in a sleeved mode.
According to a preferred embodiment, the organic glass layer cup joints outside the tungsten alloy layer, organic glass layer outer wall have be equipped with along 1 axial direction's of body scale, spacing portion 3 cup joints in 1 outer wall of body. Along 1 axial direction of body the organic glass layer cross-section is right triangle or right trapezoid. The section of the tungsten alloy layer along the axial direction of the pipe body 1 is a right-angled triangle. The thickness of the organic glass layer is increased along the direction far away from the cover plate 4, and the thickness of the tungsten alloy layer is reduced. The contact surface of the organic glass layer and the tungsten alloy layer is a conical surface, and the organic glass layer and the tungsten alloy layer jointly form a cylindrical pipe body 1. The included angle between the contact conical surface of the organic glass layer and the tungsten alloy layer and the central line of the pipe body 1 in the axial direction is 30-90 degrees. The distance between the edge of the cylindrical groove arranged on the bottom plate 2 and the inner wall of the pipe body 1 is larger than the maximum thickness of the tungsten alloy layer. So that the gamma rays of the radioactive sample located in the cylindrical recess of the base plate 2 pass through the tubular body 1, the thickness of the tungsten alloy layer corresponding to the position where the gamma rays strike the tubular body 1 becomes thinner the farther away from the base plate 2 or the radioactive sample. Thereby avoiding the use of tungsten alloy with the same thickness for shielding the radioactivity of the radioactive sample in the whole tube body. The purpose of saving tungsten alloy materials and reducing the weight of the bracket is achieved, so that the bracket is more convenient to carry and more suitable for field radioactivity measurement. According to a preferred embodiment, the inner diameter of the tubular body 1 according to the invention is 77.5 mm. An outer diameter of 90mm, a wall thickness of 6.25mm and a length of 84 mm. According to a preferred embodiment, the tungsten alloy used in the invention is a wolfram-nickel-iron alloy, which is an alloy based on tungsten (about 90-98%) and added with nickel and iron components, wherein the nickel-iron ratio is generally 7: 3.
the bottom plate 2 in the support structure is a cylindrical disc. The bottom plate 2 is positioned in the pipe body 1. The central axis of the disc of the bottom plate 2 coincides with the central axis of the tube body 1. The bottom plate 2 is rigidly connected with the pipe body 1 and the cover plate 4. The bottom plate 2 is provided with a step-shaped cylindrical groove, the diameter of the groove is smaller when the bottom plate is closer to the cover plate 4, and the cylindrical groove and the disc 2 have the same central axis. The different diameters of the stepped cylindrical grooves correspond to the diameters of the sample boxes for containing radioactive samples to be tested. Therefore, the measurement of multi-specification samples is realized. The bottom plate 2 is made of organic glass or tungsten alloy. According to a preferred embodiment, the bottom plate 2 has a diameter of 77.5 mm. The thickness of the bottom plate 2 is 22 mm.
The limiting part 3 in the support structure is a cylindrical tubular structure. The limiting part 3 is sleeved outside the pipe body 1 and is rigidly connected with the pipe body 1. The central axis of the limiting part 3 coincides with the central axis of the pipe body 1. The central axis of the limiting part 3 is perpendicular to the circular plane of the cover plate 4. According to a preferred embodiment, the inner diameter of the limiting part 3 is 90mm, which is equal to the outer diameter of the pipe body 1, the outer diameter of the limiting part 3 is 104.5mm, the wall thickness is 7.25mm, and the length of the limiting part 3 is 24 mm.
The cover plate 4 in the support structure is a cylindrical disc structure. The circular end faces of the discs of the cover plate 4 comprise a first end face and a second end face. The first end face is connected with the pipe body 1 and the bottom plate 2, and the second end face is connected with the pull rod 5. The cover plate 4 is coaxial with the pipe body 1, the bottom plate 2 and the limiting part 3. According to a preferred embodiment, the first end face of the cover plate 4 is provided with a circular groove, the inner wall of the groove is provided with internal threads, the outer wall of the pipe body 1 close to the cover plate 4 is provided with external threads, the pipe body 1 is connected with the cover plate 4 through a thread meshing relationship, and the diameter of the cover plate 4 is 114.5mm and the thickness of the cover plate 4 is 10 mm.
The pull rod 5 in the support structure is of a cylindrical structure. The pull rod 5 is connected with the second end face of the cover plate 4. The pull rod 5 is coaxial with the cover plate 4. Meanwhile, the pull rod 5 is provided with an annular groove 6 with a rectangular radial section. According to a preferred embodiment, the tie rod 5 is provided with at least one annular groove having a rectangular cross section in the radial direction of the tie rod 5. According to a preferred embodiment, the tie rod 5 has a diameter of 40mm and a length of 30 mm.
Fig. 2 shows a schematic structural diagram of a fixed support and a detector in a matching relationship for rapidly measuring an environmental sample according to the invention. As shown in fig. 2, the figure at least includes a detector 8 and a fixing bracket. The detector 8 at least comprises a probe 11, an electronics part 10 and a refrigeration part. The probe 11 is connected to the electronics 10. The detector 8 collects gamma photons through the probe 11 and converts the gamma photons into an output signal through the electronics part 10, so that the radioactivity of the sample to be measured is quantitatively measured. The probe 11 is also connected with a refrigerating part, and the probe crystal is ensured to work under the optimum condition through the refrigerating part. The refrigeration mode of the refrigeration part comprises liquid nitrogen refrigeration or electric refrigeration. The probe 11 at least comprises a beryllium window 12 and a detection crystal, wherein the detection crystal can be one of HPGe, NaI, CsI and CdTe.
According to a preferred embodiment, the detector selected for use in the present invention is an HPGe detector. The detection crystal adopts HPGe crystal, and the thickness of the beryllium window 12 is 0.5 mm. Since the energy band interval of Ge is only 0.665eV, the large amount of leakage current caused by the thermal motion of molecules can not make any Ge detector work at room temperature, and the detector must be placed at a certain low temperature to work, so that the noise caused by the leakage current can not destroy the ionization energy. The leakage current starts to rise obviously at-163 ℃ to-153 ℃, and in addition, a field effect tube and a charge sensitive feedback element which are used as input stages of a preamplifier of the detector are also required to be placed at low temperature, namely a capacitor and a parallel high-resistance or a transistor switch which are connected with a detection crystal are also required to be placed at low temperature, so that the influence of noise caused by the thermal motion of other molecules on the detection resolution is reduced as much as possible. For most germanium detectors at present, cryogenic temperatures are achieved by inserting multiple cooling pins into thermal contact with liquid nitrogen at-196 ℃. Due to design differences in various refrigeration results, the actual operating temperature of the HPGe detector is between about-188 ℃ and-163 ℃. According to a preferred embodiment, the detector 8 of the present invention adopts a portable electric refrigeration detector, and the problem of inconvenient carrying of liquid nitrogen during field measurement in various complex environments is avoided by electric refrigeration.
In the process of utilizing the detector 8 to measure the field radioactivity of the environmental sample, the detector 8 and the fixed support are horizontally placed, wherein a probe 11 of the detector 8 is coaxial with the support tube body 1 or the sample groove 7. The pipe body 1 is sleeved on a probe 11 of the detector 8. The diameter of the tube body 1 is slightly larger than that of the probe 12, and the difference is 0.5-1 mm. According to a preferred embodiment, the length of the sample slot 7 formed in the tubular body 1 is greater than or equal to the sum of the length of the probe 11 and the height of the sample box for containing the radioactive environmental sample, so as to ensure that the sample box does not contact the beryllium window 12 on the probe 11 during the measurement process or the sample replacement process, thereby avoiding damage to the beryllium window 12. During the measurement, the end face of the pipe body 1 far away from the cover plate 4 is in contact with the end face of the probe end of the electronics unit 10. The support makes spacing portion 3 and the preceding terminal surface 9 contact of refrigeration portion through adjusting spacing portion 3 to continue along the spacing portion 3 of rotation of 8 directions of detector, thereby make the support remove along the direction that deviates from detector 8, its displacement accessible is located the scale reading on the body 1 outer wall. That is, after the front end surfaces of the limiting part 3 and the cooling part 9 contact, the distance that the limiting part 3 continues to move along the direction of the detector 8 is the distance that the fixed bracket moves away from the detector 8. The length of the limiting part 3 is smaller than that of the probe 11, and the purpose of the limiting part is to prevent the pipe body 1 from being separated from the probe 11 in the process that the fixed support moves in the reverse direction relative to the detector 8, so that the pipe body 1 damages the beryllium window 12 of the probe 11. The length of spacing portion 3 is greater than the thickness value of electronics portion 10 for spacing portion 3 can stretch out and contact terminal surface 9 before the refrigeration portion from body 1, thereby can realize the removal of fixed bolster for detector 8 through the effect of the mutual force of spacing portion 3 and terminal surface 9 before the refrigeration portion. According to another preferred embodiment, the support can also be fixed by lead shielding means, with its tubular body 1 coaxial with the probe 11.
Example 1
The fixed support of the invention is used for assisting in rapidly measuring the radioactive sample to be measured on the sample collection site. In the radioactive environment sample measurement process, the measurement component comprises a radioactive detector, a bracket and a radioactive environment sample.
The diameter of the bracket tube body 1 is slightly larger than that of the cylindrical probe of the detector, and the difference value is 0.5-1 mm. During the measurement, the cylindrical probe is coaxial with the body 1 of the stent. The pipe body 1 is composed of an organic glass layer and a tungsten alloy layer, and the organic glass layer is sleeved outside the tungsten alloy layer. The tungsten alloy layer can be in occlusion connection with the organic glass layer through threads. The tube body 1 is provided with a tungsten alloy layer structure, so that the influence of natural radioactive substances or natural background in the environment in the field radioactivity measurement process on the measurement process is effectively shielded, and meanwhile, the tungsten alloy layer structure also plays a role in shielding a radioactive sample to be measured, and avoids radioactive damage to measuring personnel. According to the radioactive intensity of the environmental sample to be measured, the thickness of the tungsten alloy structural layer in the tube body 1 is selected to be 0-6 mm.
The organic glass layer cup joints outside the tungsten alloy layer, organic glass layer outer wall has and is equipped with the edge the 1 axial direction's of body scale, spacing portion 3 cup joint in 1 outer wall of body. The thickness of the organic glass layer is increased along the direction far away from the cover plate 4, and the thickness of the tungsten alloy layer is reduced. The organic glass layer is a right triangle and/or a right trapezoid. The section of the tungsten alloy layer is a right-angled triangle. The contact surface of the organic glass layer and the tungsten alloy layer is a conical surface, and the organic glass layer and the tungsten alloy layer jointly form a cylindrical pipe body 1. The included angle between the contact conical surface of the organic glass layer and the tungsten alloy layer and the central line of the tube body 1 in the axial direction is 30 degrees. The distance between the edge of the cylindrical groove arranged on the bottom plate 2 and the inner wall of the pipe body 1 is larger than the maximum thickness of the tungsten alloy layer.
In the process of measuring the radioactivity of the environmental sample, the sample to be measured is placed in a sample box, the sample box is placed in a sample groove 7 of the support, and the sample box is placed in a cylindrical groove corresponding to the bottom plate 2 according to the diameter of the sample box. The detector is horizontally placed, and a cylindrical probe of the radioactive detector is inserted into a sample groove 7 of the tube body 1. The length of the sample groove 7 formed in the pipe body 1 is larger than or equal to the sum of the length of the probe 11 and the height of a sample box for containing a radioactive environment sample, so that the sample box can not contact the beryllium window 12 on the probe 11 in the measuring process or the sample replacing process of the detector 8, and the beryllium window 12 is prevented from being damaged. After the probe 11 of the detector 8 is completely inserted into the sample groove 7, the end face, far away from the cover plate 4, of the pipe body 1 is in contact with the end face of the probe end of the electronics part 10, the bracket makes the limiting part 3 in contact with the front end face 9 of the refrigeration part by adjusting the limiting part 3, and continues to rotate the limiting part 3 along the direction of the detector 8, so that the bracket can move along the direction away from the detector 8, and the moving distance can be read by a scale located on the outer wall of the pipe body 1.
Based on the scale that sets up on the outer wall of body 1 along the axial direction, realize spacing portion 3 for the accurate removal of body 1 to realize the sample in sample groove 7 and the accurate adjustable of detector probe position. And opening the detector to finish the measurement of the radioactive sample to be measured. Meanwhile, the user can realize the function of inserting or extracting the detector 8 into or from the bracket based on the pull rod 5. Meanwhile, in the process of replacing a sample or repeatedly measuring, as long as the position of the limiting part 3 relative to the pipe body 1 is determined to be unchanged, the relative position of the sample to be measured and the probe 11 of the detector 8 can be unchanged, so that the inconsistency of the measurement geometric conditions of the sample and a standard radioactive source cannot be ensured in the process of measuring radioactivity is avoided. And the problem that different workers in the experiment process have large artificial uncertain factors due to non-standard operation, personnel factors and other reasons in the measurement process, so that large errors are finally brought to the measurement result is solved.
Example 2
The fixed support of the present invention is used to assist in measuring the radioactivity of an environmental sample. The measurement components include a radioactivity detector 8, a lead shielding structure, a support, and a radioactive environment sample. The radioactivity detector has a cylindrical probe 11. The lead shielding structure is a cubic lead shielding structure with a cylindrical through hole, the diameter of the cylindrical through hole is slightly larger than that of the pipe body 1, and the difference value is 0.5-1 mm. The tube body 1 is made of organic glass.
The measuring process comprises the following steps: the cylindrical probe 11 of the radioactivity measuring probe is inserted into the lead shielding structure through the lead shielding cylindrical through hole. The detector 8 is horizontally arranged, and the central axis of the lead shielding cylindrical through hole is in the horizontal direction. Meanwhile, the length of the lead shielding cylindrical through hole is larger than the length of the probe 11 of the detector 8 penetrating into the lead shielding structure. The radioactive environment sample to be tested is placed in the sample well 7 of the support structure. And inserting the pipe body 1 of the support into the lead shielding structure along the other end of the lead shielding through hole. The insertion depth of the bracket is adjusted and controlled by the limiting part 3. And opening the detector to finish the measurement of the radioactive sample to be measured. Meanwhile, the user can realize the function of inserting or extracting the lead shielding structure of the bracket based on the pull rod 5. Meanwhile, a pull rope or other connecting belts can be tied in the groove 6 on the pull rod 5 to realize the function of pulling the bracket to move. Meanwhile, in the process of replacing a sample or repeatedly measuring, as long as the position of the limiting part 3 is determined to be unchanged, the relative position of the sample to be measured and the probe of the detector can be unchanged, so that the inconsistency that the measurement geometric conditions of the sample and a standard radioactive source cannot be ensured in the process of measuring radioactivity is avoided. And the problem that different workers in the experiment process have large artificial uncertain factors due to non-standard operation, personnel factors and other reasons in the measurement process, so that large errors are finally brought to the measurement result is solved.
Example 3
On the basis of embodiment 2, a description will be given by taking an example in which the fixing bracket of the present invention fixes the measurement position of the environmental sample to be measured. In the radioactive environment sample measurement process, the measurement components include the radioactivity detector 8, the lead shielding structure, the support, and the radioactive environment sample. The radiation detector 8 has a cylindrical probe 11. The lead shielding structure is a cubic lead shielding structure with a cylindrical through hole. The diameter of the cylindrical through hole is slightly larger than that of the pipe body 1, and the difference value is 0.5-1 mm. The diameter of the cylindrical through hole is larger than that of the cylindrical probe 11 of the radioactive detector. During measurement, the cylindrical probe is coaxial with the cylindrical through hole of the lead shield. I.e. the cylindrical probe is coaxial with the tubular body 1 of the stent.
According to a preferred embodiment, the outer wall of the tie rod 5 may be provided with a plurality of annular grooves. The section of the annular groove in the radial direction of the pull rod 5 is a rectangular section. The groove is used for increasing the contact area between the hand of a user and the pull rod 5 in the using process, so that the friction force is increased, and the user can move the support through the pull rod 5 more easily. According to a preferred embodiment, the tie rod 5 may also be of cubic construction. According to a preferred embodiment, the end face of the cover plate 4 may be of an elliptical or rectangular configuration.
In the measuring process of the radioactive environment sample, the sample to be measured is placed in the sample box, the sample box is placed in the sample groove 7 of the support, and the sample box is placed in the cylindrical groove corresponding to the bottom plate 2 according to the diameter of the sample box. The bracket is inserted into the cylindrical through hole of the lead shielding structure, so that a sample to be detected enters a position to be detected. The position of the sample to be detected and the position of the detector are relatively fixed by the limiting part 3 of the bracket. The limiting part 3 is sleeved on the outer wall of the pipe body 1. The limiting part 3 is in rigid connection with the pipe body 1.
According to a preferred embodiment, the outer wall of the pipe body 1 is provided with external threads, the inner wall of the limiting part 3 is provided with internal threads, and the limiting part 3 is sleeved on the outer wall of the pipe body 1 based on a thread meshing relationship. Thereby realized spacing portion 3 along the function of body 1 axial direction removal, realized that the sample in sample groove 7 and detector probe position are adjustable to the function of repeatedly fixing a position.
According to a preferred embodiment, the outer wall of the tube 1 is provided with a scale in the axial direction. With the scale zero point located at the port near one end of the cover plate 4. The accurate movement of the limiting part 3 relative to the pipe body 1 can be realized through the ruler, so that the accurate adjustment of the positions of the sample in the sample groove 7 and the probe of the detector is realized. Therefore, the accurate measurement of the distance between the probe and the radioactive sample to be measured can be realized or the position variation of the radioactive sample to be measured and the probe of the detector can be measured by measuring the depth of the probe of the detector inserted into the lead shielding structure, the length of the lead shielding cylindrical through hole and the scale corresponding to the limiting part 3. The function of accurately adjusting or measuring the relative position of the sample in the sample groove 7 and the probe of the detector is realized. The radioactive measurement device can meet more requirements of energy scales, efficiency scales and actual measurement in the radioactive measurement process.
It should be noted that the above-mentioned embodiments are exemplary, and that those skilled in the art, having benefit of the present disclosure, may devise various arrangements that are within the scope of the present disclosure and that fall within the scope of the invention. It should be understood by those skilled in the art that the present specification and figures are illustrative only and are not limiting upon the claims. The scope of the invention is defined by the claims and their equivalents.
Claims (10)
1. A method of using a stationary support for radioactive measurements, comprising performing a measurement of a radioactive sample using a probe (8), a lead-shielding structure and a stationary support,
it is characterized in that the preparation method is characterized in that,
the detector (8) is provided with a cylindrical probe (11), the lead shielding structure is a cubic lead shielding structure with a cylindrical through hole,
the bracket at least comprises: the support is characterized in that the support is of a cup-shaped structure, a cylindrical cup wall is formed by the pipe body (1) and the limiting part (3), and a cup seat is formed by the cover plate (4) and the pull rod (5);
the pipe body (1) is sleeved outside a probe (11) of the detector (8), the end face, far away from the cover plate (4), of the pipe body (1) is in contact with the end face of the probe end of the electronics part (10), the limiting part (3) of the bracket is made to be in contact with the front end face (9) of the refrigeration part by adjusting the limiting part (3), the limiting part (3) is made to continue to move along the direction of the detector (8), the bracket is made to move along the direction far away from the detector (8), and the moving distance of the bracket is read through a scale on the outer wall of the pipe body (1);
the pipe body (1) is at least a double-structure layer formed by an organic glass layer and a tungsten alloy layer, the organic glass layer is sleeved outside the tungsten alloy layer, a scale along the axial direction of the pipe body (1) is arranged on the outer wall of the organic glass layer, and the limiting part (3) is sleeved on the outer wall of the pipe body (1);
the thickness of the organic glass layer of the tube body (1) is increased along the direction far away from the cover plate (4), the thickness of the tungsten alloy layer is reduced, the cross section of the organic glass layer and the tungsten alloy layer along the axial direction of the tube body (1) is a right triangle and/or a right trapezoid, the contact surface of the organic glass layer and the tungsten alloy layer is a conical surface, and the organic glass layer and the tungsten alloy layer jointly form a cylindrical tube body (1);
the included angle between the contact conical surface of the organic glass layer and the tungsten alloy layer and the central line of the tube body (1) in the axial direction of the tube body (1) is 30-90 degrees, and the distance between the edge of the cylindrical groove arranged on the bottom plate (2) and the inner wall of the tube body (1) is greater than the maximum thickness of the tungsten alloy layer;
apron (4) are cylindrical disc structure, apron (4) disc terminal surface includes first terminal surface and second terminal surface, first terminal surface links to each other with body (1) and bottom plate (2), the second terminal surface links to each other with pull rod (5), bottom plate (2) are located body (1), bottom plate (2) are discoid structure, bottom plate (2) with body (1) have constituted sample groove (7) jointly.
2. The use method according to claim 1, wherein the tungsten alloy layer in the pipe body (1) is in occlusion connection with the organic glass layer through threads, wherein the thickness of the tungsten alloy layer is 0-6 mm; the outer wall of the pipe body (1) is provided with a scale along the axial direction, and the zero point of the scale is located at a port close to one end of the cover plate (4).
3. Use according to claim 1, wherein the depth of the sample well (7) formed by the tubular body (1) is greater than or equal to the sum of the length of the probe (11) and the height of the sample box for containing the environmental sample, and the diameter of the tubular body (1) is slightly greater than the diameter of the probe (11) by a difference of 0.5 to lmm.
4. Use according to claim 1, wherein the length of the stop portion (3) has a value less than the length of the probe (11) and the length of the stop portion (3) has a value greater than the thickness of the electronics portion (10).
5. The use method according to claim 1, wherein the central axis of the pipe body (1) is perpendicular to the cover plate (4), the limiting portion (3) is a cylindrical tubular structure, wherein the outer wall of the pipe body (1) is provided with external threads, the inner wall of the limiting portion (3) is provided with internal threads, the limiting portion (3) is sleeved on the outer wall of the pipe body (1) based on a thread engagement relationship, the central axis of the limiting portion (3) is coincident with the central axis of the pipe body (1), and the central axis of the limiting portion (3) is perpendicular to the cover plate (4).
6. The use method as claimed in claim 1, characterized in that the end surface of the bottom plate (2) facing the sample chamber (7) is provided with at least one step-shaped cylindrical groove, the diameter of the groove is smaller as the groove is closer to the cover plate (4), the different diameters of the different step-shaped grooves correspond to the diameter of a sample box for containing the radioactive sample to be measured, and the material of the bottom plate (2) is at least one of organic glass or tungsten alloy;
the bottom plate (2) disc central axis coincides with the pipe body (1) central axis, and the bottom plate (2) is rigidly connected with the pipe body (1) and the cover plate (4).
7. The use according to claim 1, characterized in that the tie rod (5) is of cylindrical configuration, the tie rod (5) being connected to the second end face of the cover plate (4), the tie rod (5) being coaxial with the cover plate (4).
8. Use according to claim 7, characterised in that the tie rod (5) is provided with an annular groove (6) having a square cross-section in the radial direction of the tie rod (5).
9. Use according to claim 7, characterised in that the tie rod (5) is provided with at least one annular groove of rectangular cross-section in the radial direction of the tie rod (5).
10. The use method according to claim 1, characterized in that the depth value of the sample groove (7) formed by the tube body (1) is greater than or equal to the sum of the length value of the probe (11) and the height value of the sample box for containing the environmental sample, the diameter of the tube body (1) is slightly greater than the diameter of the probe (11), and the difference is 0.5-lmm;
the end face, facing the sample groove (7), of the bottom plate (2) is provided with at least one stage of stepped cylindrical groove, the diameter of the groove is smaller when the groove is closer to the cover plate (4), the different diameters of the stepped grooves of different stages correspond to the diameter of a sample box for containing a radioactive sample to be detected, and the bottom plate (2) is made of at least one of organic glass or tungsten alloy;
the limiting part (3) is of a cylindrical tubular structure, wherein the outer wall of the pipe body (1) is provided with an external thread, the inner wall of the limiting part (3) is provided with an internal thread, the limiting part (3) is sleeved on the outer wall of the pipe body (1) based on a thread engagement relation, the central axis of the limiting part (3) is overlapped with the central axis of the pipe body (1), the central axis of the limiting part (3) is perpendicular to the cover plate (4), the length value of the limiting part (3) is smaller than that of the probe (11), and the length value of the limiting part (3) is larger than that of the electronics part (10);
the cover plate (4) is coaxial with the pipe body (1), the bottom plate (2) and the limiting part (3);
the pull rod (5) is of a cylindrical structure, the pull rod (5) is connected with the second end face of the cover plate (4), the pull rod (5) is coaxial with the cover plate (4), and at least one annular groove with a rectangular cross section in the radial direction of the pull rod (5) is formed in the pull rod (5).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811351807.4A CN109298440B (en) | 2016-10-26 | 2016-10-26 | Using method of fixing support for radioactivity measurement |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811351807.4A CN109298440B (en) | 2016-10-26 | 2016-10-26 | Using method of fixing support for radioactivity measurement |
| CN201610948413.1A CN106291658B (en) | 2016-10-26 | 2016-10-26 | A kind of fixing bracket of on-site rapid measurement environmental sample |
Related Parent Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610948413.1A Division CN106291658B (en) | 2016-10-26 | 2016-10-26 | A kind of fixing bracket of on-site rapid measurement environmental sample |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109298440A CN109298440A (en) | 2019-02-01 |
| CN109298440B true CN109298440B (en) | 2020-03-27 |
Family
ID=57719414
Family Applications (5)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811351808.9A Active CN109298441B (en) | 2016-10-26 | 2016-10-26 | Detection apparatus suitable for radioactive sample |
| CN201610948413.1A Active CN106291658B (en) | 2016-10-26 | 2016-10-26 | A kind of fixing bracket of on-site rapid measurement environmental sample |
| CN201811351807.4A Active CN109298440B (en) | 2016-10-26 | 2016-10-26 | Using method of fixing support for radioactivity measurement |
| CN201811351806.XA Active CN109298439B (en) | 2016-10-26 | 2016-10-26 | Rapid detection system based on radioactivity measurement |
| CN201811351809.3A Active CN109298442B (en) | 2016-10-26 | 2016-10-26 | Rapid measurement method of environmental sample |
Family Applications Before (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811351808.9A Active CN109298441B (en) | 2016-10-26 | 2016-10-26 | Detection apparatus suitable for radioactive sample |
| CN201610948413.1A Active CN106291658B (en) | 2016-10-26 | 2016-10-26 | A kind of fixing bracket of on-site rapid measurement environmental sample |
Family Applications After (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811351806.XA Active CN109298439B (en) | 2016-10-26 | 2016-10-26 | Rapid detection system based on radioactivity measurement |
| CN201811351809.3A Active CN109298442B (en) | 2016-10-26 | 2016-10-26 | Rapid measurement method of environmental sample |
Country Status (1)
| Country | Link |
|---|---|
| CN (5) | CN109298441B (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111411935A (en) * | 2020-04-09 | 2020-07-14 | 李国栋 | Gamma logger field coefficient checker |
| CN113484896B (en) * | 2021-07-01 | 2024-05-10 | 成都纽瑞特医疗科技股份有限公司 | Radioactive substance detection device |
| CN113777173A (en) * | 2021-08-20 | 2021-12-10 | 西北工业大学 | Ultrasonic nonlinear measurement clamping device and measurement method thereof |
| CN114055363B (en) * | 2021-11-19 | 2023-04-14 | 中国工程物理研究院核物理与化学研究所 | Pneumatic clamp for measuring radioactive cylindrical sample |
| CN114509462A (en) * | 2022-02-18 | 2022-05-17 | 中国核动力研究设计院 | Scanning electron microscope shielding sample holder and system for radioactive test sample |
| CN114518376B (en) * | 2022-02-18 | 2024-08-23 | 中国核动力研究设计院 | Electron probe shielding sample seat for radioactive sample |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5610300A (en) * | 1979-07-04 | 1981-02-02 | Mitsubishi Electric Corp | Check ray source device |
| CN102138083A (en) * | 2008-07-14 | 2011-07-27 | Icx科技有限责任公司 | Detector system with positioning system |
| CN104570049A (en) * | 2014-12-18 | 2015-04-29 | 中国船舶重工集团公司第七一九研究所 | Calibration tool for radiation detector |
| CN204631258U (en) * | 2015-04-22 | 2015-09-09 | 北京华泰诺安科技有限公司 | A kind of jamproof nuclear radiation detects extension rod |
| CN204705720U (en) * | 2015-04-16 | 2015-10-14 | 舟山出入境检验检疫局综合技术服务中心 | A kind of gamma spectrometer sample testing frame with self-cleaning function |
| CN105203567A (en) * | 2015-10-23 | 2015-12-30 | 苏州晶特晶体科技有限公司 | Visibly adjusted high-energy ray detector |
Family Cites Families (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1438431A (en) * | 1965-03-30 | 1966-05-13 | Commissariat Energie Atomique | Method and device for the determination of liquid volumes by dilution of a radioactive solution |
| US4039809A (en) * | 1975-09-02 | 1977-08-02 | Bailey Sylvia M | Lower-energy neutron sources for increasing the sensitivity of nuclear gages for measuring the water content of bulk materials |
| JP3397030B2 (en) * | 1996-01-23 | 2003-04-14 | 富士電機株式会社 | Radiation detector for high temperature incinerator monitor |
| JP5089568B2 (en) * | 2008-12-22 | 2012-12-05 | 三菱電機株式会社 | Radioactive gas monitor |
| CN202177702U (en) * | 2011-08-05 | 2012-03-28 | 湖北方圆环保科技有限公司 | Shielding lead chamber of low-background gamma energy disperse spectroscopy |
| CN203101653U (en) * | 2013-02-26 | 2013-07-31 | 珠海出入境检验检疫局检验检疫技术中心 | Jacket-type sample swager for radionuclide Gamma energy spectrum analysis |
| CN203551791U (en) * | 2013-09-27 | 2014-04-16 | 中国人民解放军济南军区装备部防化技术室 | Portable gamma spectrometer and gamma spectrum specific activity measuring device |
| CN105793713B (en) * | 2013-10-09 | 2018-01-05 | 株式会社日立制作所 | Specimen Determination device |
| CN203759254U (en) * | 2014-03-18 | 2014-08-06 | 西北核技术研究所 | Flat source box for efficiency calibration of gram-scale solid powder sample |
| JP6234299B2 (en) * | 2014-03-28 | 2017-11-22 | 三菱電機株式会社 | Radioactive gas monitor |
| JP6501139B2 (en) * | 2014-11-10 | 2019-04-17 | セイコー・イージーアンドジー株式会社 | Radiation detector support stand |
| CN105652310A (en) * | 2014-11-18 | 2016-06-08 | 中国辐射防护研究院 | Movable liquid effluent monitoring device with optimized structure |
| CN104820230B (en) * | 2015-04-24 | 2018-01-05 | 中国船舶重工集团公司第七一九研究所 | A kind of Low background α, β activity analysis instrument |
| CN105223604B (en) * | 2015-10-28 | 2020-02-28 | 清华大学 | Low background gamma energy spectrum analysis device |
| CN205246888U (en) * | 2015-12-10 | 2016-05-18 | 国家海洋局第三海洋研究所 | Water environment radionuclide activity section measurement system |
| CN105866819A (en) * | 2016-05-20 | 2016-08-17 | 浙江省辐射环境监测站 | Radioactive monitoring equipment |
-
2016
- 2016-10-26 CN CN201811351808.9A patent/CN109298441B/en active Active
- 2016-10-26 CN CN201610948413.1A patent/CN106291658B/en active Active
- 2016-10-26 CN CN201811351807.4A patent/CN109298440B/en active Active
- 2016-10-26 CN CN201811351806.XA patent/CN109298439B/en active Active
- 2016-10-26 CN CN201811351809.3A patent/CN109298442B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5610300A (en) * | 1979-07-04 | 1981-02-02 | Mitsubishi Electric Corp | Check ray source device |
| CN102138083A (en) * | 2008-07-14 | 2011-07-27 | Icx科技有限责任公司 | Detector system with positioning system |
| CN104570049A (en) * | 2014-12-18 | 2015-04-29 | 中国船舶重工集团公司第七一九研究所 | Calibration tool for radiation detector |
| CN204705720U (en) * | 2015-04-16 | 2015-10-14 | 舟山出入境检验检疫局综合技术服务中心 | A kind of gamma spectrometer sample testing frame with self-cleaning function |
| CN204631258U (en) * | 2015-04-22 | 2015-09-09 | 北京华泰诺安科技有限公司 | A kind of jamproof nuclear radiation detects extension rod |
| CN105203567A (en) * | 2015-10-23 | 2015-12-30 | 苏州晶特晶体科技有限公司 | Visibly adjusted high-energy ray detector |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109298441A (en) | 2019-02-01 |
| CN109298439A (en) | 2019-02-01 |
| CN109298442B (en) | 2020-03-27 |
| CN109298442A (en) | 2019-02-01 |
| CN106291658B (en) | 2018-11-06 |
| CN109298440A (en) | 2019-02-01 |
| CN109298441B (en) | 2020-03-27 |
| CN106291658A (en) | 2017-01-04 |
| CN109298439B (en) | 2020-03-27 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109298440B (en) | Using method of fixing support for radioactivity measurement | |
| KR100478251B1 (en) | Apparatus for measuring corrosion thickness of insulated pipeline | |
| US4267446A (en) | Dual scintillation detector for determining grade of uranium ore | |
| CN104820230B (en) | A kind of Low background α, β activity analysis instrument | |
| US4224517A (en) | Device for assaying uranium and/or thorium in ore specimens comprising gold foil for suppressing compton background | |
| Alnour et al. | New approach for calibration the efficiency of HpGe detectors | |
| KR100925560B1 (en) | Radiation Measurement Apparatus with Three Dimensional Movable Detector | |
| US3723727A (en) | In-situ neutron activation | |
| US8147134B2 (en) | Method and apparatus for isotope identification and radioactivity measurement of alpha-emitting-radionuclides using a low temperature detector | |
| Bae et al. | Development of continuous inflow tritium measurement in water technology using electrolysis and a plastic scintillator | |
| US3535520A (en) | Method of and apparatus for the measurement of physical characteristics of x-rays,in particular of gamma-rays,and its application | |
| CN219978537U (en) | MPPC-based radioactive waste barrel surface alpha beta ray detector | |
| Marian et al. | Electrically-cooled HPGe detector for advanced x-ray spectroscopy and imaging | |
| Sobel et al. | Characterization of PIPS detectors for measurement of radioxenon | |
| Alghamdi et al. | Designing and constructing of a two scintillator crystal rotatable telescope for muon flux variation studies | |
| Alghem et al. | NDT as a tool, for Post-Irradiation Examination | |
| Gong et al. | Discussion on the factors affecting the radioactive detection results of ceramic tiles | |
| Kadilin et al. | Detectors on base of scintillation structures for registration of volumetric activities of gaseous and liquid media gamma radiation | |
| Ti et al. | Design of a non-resonant Mössbauer scattering system at low temperatures | |
| JP6249364B2 (en) | Analytical method and analytical apparatus for transuranium elements mixed with fission products | |
| Herold | Nuclear instrumentation for curium and californium processing | |
| Gabelova et al. | STUDY OF THE RAPID TRANSMIGRATIONS OF SUBSTANCES IN AN ORGANISM USING $ gamma $-EMITTING ISOTOPES | |
| Hagan et al. | Radiation gauging at LASL | |
| Lee | Operational Characteristics of a Fission Gas Detector | |
| Franks et al. | 193 (IL) 82t 33 |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |