CN202676922U - Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89 - Google Patents

Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89 Download PDF

Info

Publication number
CN202676922U
CN202676922U CN 201220309398 CN201220309398U CN202676922U CN 202676922 U CN202676922 U CN 202676922U CN 201220309398 CN201220309398 CN 201220309398 CN 201220309398 U CN201220309398 U CN 201220309398U CN 202676922 U CN202676922 U CN 202676922U
Authority
CN
China
Prior art keywords
pig
photomultiplier
model
utility
analyzed
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
CN 201220309398
Other languages
Chinese (zh)
Inventor
姚志铨
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
NINGBO JUNAN PHARMACEUTICAL SCIENCE AND TECHNOLOGY Co Ltd
Original Assignee
NINGBO JUNAN PHARMACEUTICAL SCIENCE AND TECHNOLOGY Co Ltd
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 NINGBO JUNAN PHARMACEUTICAL SCIENCE AND TECHNOLOGY Co Ltd filed Critical NINGBO JUNAN PHARMACEUTICAL SCIENCE AND TECHNOLOGY Co Ltd
Priority to CN 201220309398 priority Critical patent/CN202676922U/en
Application granted granted Critical
Publication of CN202676922U publication Critical patent/CN202676922U/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

Landscapes

  • Measurement Of Radiation (AREA)

Abstract

The utility model relates to a rapid discriminating and nuclear purity analysis apparatus of a radionuclide Sr-89. The apparatus comprises a lead chamber, a NaI crystal, a photomultiplier, a lead pot, a plastic container, a penicillin bottle and a plastic cup. The apparatus of the utility model can rapidly discriminate the Sr-89 nuclide with a high sensitivity. Technical requirement difficulty to an operator is small. Compared with a scintillation liquid, by using the apparatus, a radioactivity waste quantity is reduced so that environment is improved. Simultaneously, investments for an enterprise to establish new equipment and an apparatus are reduced and a good application prospect is possessed.

Description

The device that a kind of radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed
Technical field
The utility model relates to Sr-89 and detects and the uclear purity analysis field, particularly relates to the device that a kind of radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed.
Background technology
The radioactive nuclide strontium-89 is directly launched 50.55 days ceiling capacity 1463Kev β ray half life period, and other decays into strontium-89 m at have an appointment 0.01% probability, and discharges energetic gamma rays (energy 909Kev), decays at last stable nuclide ytterbium-89.
By artificial radioisotope's strontium-89 ( 89Sr) strontium chloride of making (strontium-89) injection at home and abroad has been widely used in treating metastatic carcinoma of bone disease patient, alleviates its pain, improve the quality of living, its mechanism be strontium chloride [ 89Sr] solution injects in the patient body, because strontium is bone seeker, and this solution is concentrated in cancerous tissue bone metastasis site, carry out radiation cure by ceiling capacity 1463Kev high energy β ray and the irradiation of bony site sore place of strontium-89 emission, palliate the agonizing sufferings, improve the quality of living.
Commercial strontium chloride radioactive solution, wherein the discriminating of strontium-89 nucleic is generally all measured its β ray energy spectrum and highest energy (1463Kev) with liquid scintillator detector.And with standard strontium-89 β ray energy spectrum relatively, the method has been used for the departments such as scientific research because use procedure complicated operation, technical difficulty are high, time-consuming, there is certain difficulty in small business for producing frequently.
The utility model content
Technical problem to be solved in the utility model provides the device that a kind of radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, this device is quick, high sensitivity is differentiated the strontium-89 nucleic, device is little to operator's technical requirement difficulty, compare with utilizing scintillating liquid, can reduce the radioactive waste amount, to improve environment, reduce simultaneously the investment that enterprise need set up new equipment, instrument.
Of the present utility model a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, described device comprises vitriol chamber, NaI crystal and photomultiplier, pig, plastic containers, cillin bottle and plastic cup;
NaI crystal and photomultiplier are positioned among the vitriol chamber, and pig is positioned at the vitriol chamber top, and plastic containers are positioned among the pig, and plastic cup is positioned among the plastic containers, and cillin bottle is positioned among the plastic cup;
Pig thickness is 15mm, and plastic containers are the nylon tank of wall thickness 8mm, and sample liquids height and vitriol chamber distance is 80mm in the cillin bottle.
The end of described nylon tank is the 14mm organic glass.
Described vitriol chamber thickness is 100mm.
The diameter of described NaI crystal and photomultiplier is 50mm.
Described plastic cup thickness is 1mm.
The distance of described NaI crystal and photomultiplier and pig is 40mm.
The utility model core is to manage to reduce bremsstrahlung intensity, adopt two kinds of measures, one selects light material to stop (absorption) strontium-89 high energy β, its emission bremsstrahlung strength decreased (is compared with metal material, can reduce by 1 times), its dual-purpose high atomic number metal (such as lead) shielding low-energyγ-ray can greatly increase strontium-89 sample activity amount to be measured and shortens the discriminating Measuring Time.
Key point of the present utility model:
1) type selecting of activity meter and strontium-89 activity are demarcated (deviation is no more than 10%)
Owing to there being the gamma-ray magazine nucleic of trace (being less than 0.1%) emission in the strontium-89 nucleic, the efficient that activity meter is surveyed γ more than the high decades of times of efficient of measuring strontium-89 β to hundreds of times, to disturb strontium-89 activity measurement correctness, and the two efficient is than relevant with the activity meter type, compare FJ391A2 and two kinds of model activity meters of RM-905a, the former reaches 100 times, approximately 10 times of the latter to the ratio of surveying γ and survey β efficient, and the former surveys the strontium-89 poor sensitivity in the latter, therefore select RM-905a suitable.
Simultaneously, it is relevant with strontium chloride (strontium-89) liquor capacity, shape, chamber wall material, wall thickness etc. that activity meter is measured correctness.Liquor capacity should be greater than 2ml, and wall thickness should be able to full-shield β ray.
2) gamma energy spectrometer is selected and energy ~ relationship between efficiency mensuration
Utilize existing NaI gamma spectrum, although energy resolution is not so good as semiconductor energy spectrometer, owing to only measuring monoenergetic (909Kev) γ, exist without the multi-energy stack, and inexpensive, easy to use.
3) light material shield kind and wall thickness are selected
In order to reduce bremsstrahlung intensity as far as possible, select the material of atomic number Z minimum, such as water, paraffin, plastics etc., the utility model is selected the plastic shielded tank of thickness 8mm, and it can all block the β ray.
4) shielding low-energyγ-ray shielding material and thickness are selected
The low energy end of bremsstrahlung (energy 500Kev is following) radiation is extremely strong, English is that energy spectrometer numeration loss is large, cause the strontium-89 sample activity to be measured can not be too large, to increase Measuring Time, for this reason very important in the heavy metal material of plastic shielded tank outsourcing absorption low-energyγ-ray, but masking low energy γ simultaneously, unlikelyly again weakening too many 909Kev γ.It is that the best can make strontium-89 sample activity reach hundreds of millicuries that the utility model is selected thickness 15mm pig, and 909Kev γ loses approximately 10%, and greatly shortens Measuring Time.
Beneficial effect
The utility model fast, high sensitivity differentiates the strontium-89 nucleic, install littlely to operator's technical requirement difficulty, and utilizes the scintillating liquid comparison, can reduce the radioactive waste amount, to improve environment, reduce simultaneously the investment that enterprise need set up new equipment, instrument, have a good application prospect.
Description of drawings
Fig. 1 is the schematic diagram of the utility model device;
Fig. 2 is the Sr-89 decay scheme.
Embodiment
Below in conjunction with specific embodiment, further set forth the utility model.Should be understood that these embodiment only are used for explanation the utility model and are not used in the scope of the present utility model that limits.Should be understood that in addition those skilled in the art can make various changes or modifications the utility model after the content of having read the utility model instruction, these equivalent form of values fall within the application's appended claims limited range equally.
Embodiment 1
By shown in Figure 1, present embodiment relates to the device that a kind of radioactive nuclide Sr-89 differentiates fast, comprises the vitriol chamber 1 of 100mm, NaI crystal that diameter is 50mm and the plastic cup 6 of photomultiplier 2, pig 3, plastic containers 4, cillin bottle 5 and 1mm; NaI crystal and photomultiplier 2 are positioned among the vitriol chamber 1, and pig 3 is positioned at vitriol chamber 1 top, and plastic containers 4 are positioned among the pig 3, and plastic cup 6 is positioned among the plastic containers 4, and cillin bottle 5 is positioned among the plastic cup 6; Pig 3 thickness are 15mm, and plastic containers 4 are the nylon tank of wall thickness 8mm (end is the 14mm organic glass), and sample liquids height and vitriol chamber 1 distance are 80mm in the cillin bottle 5; NaI crystal and photomultiplier 2 are 40mm with the distance of pig 3.

Claims (6)

1. one kind is used for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, and it is characterized in that: described device comprises vitriol chamber (1), NaI crystal and photomultiplier (2), pig (3), plastic containers (4), cillin bottle (5) and plastic cup (6);
NaI crystal and photomultiplier (2) are positioned among the vitriol chamber (1), pig (3) is positioned at vitriol chamber (1) top, plastic containers (4) are positioned among the pig (3), and plastic cup (6) is positioned among the plastic containers (4), and cillin bottle (5) is positioned among the plastic cup (6);
Pig (3) thickness is 15mm, and plastic containers (4) are the nylon tank of wall thickness 8mm, and sample liquids height and vitriol chamber (1) distance is 80mm in the cillin bottle (5).
2. according to claim 1 a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, it is characterized in that: the end of described nylon tank is the 14mm organic glass.
3. according to claim 1 a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, it is characterized in that: described vitriol chamber (1) thickness is 100mm.
4. according to claim 1 a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, it is characterized in that: the diameter of described NaI crystal and photomultiplier (2) is 50mm.
5. according to claim 1 a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, it is characterized in that: described plastic cup (6) thickness is 1mm.
6. according to claim 1 a kind of for the device that radioactive nuclide Sr-89 differentiates fast and uclear purity is analyzed, it is characterized in that: described NaI crystal and photomultiplier (2) are 40mm with the distance of pig (3).
CN 201220309398 2012-06-28 2012-06-28 Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89 Expired - Lifetime CN202676922U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN 201220309398 CN202676922U (en) 2012-06-28 2012-06-28 Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN 201220309398 CN202676922U (en) 2012-06-28 2012-06-28 Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89

Publications (1)

Publication Number Publication Date
CN202676922U true CN202676922U (en) 2013-01-16

Family

ID=47497819

Family Applications (1)

Application Number Title Priority Date Filing Date
CN 201220309398 Expired - Lifetime CN202676922U (en) 2012-06-28 2012-06-28 Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89

Country Status (1)

Country Link
CN (1) CN202676922U (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102736098A (en) * 2012-06-28 2012-10-17 宁波君安药业科技有限公司 Method and device for identifying radionuclide Sr-89 and analyzing nuclear purity
CN107076860A (en) * 2014-05-28 2017-08-18 索列丹斯弗莱西奈公司 Radioactive material is determined
CN111999763A (en) * 2020-08-26 2020-11-27 山西医科大学 Accommodating device, activity detection station and activity detection method

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102736098A (en) * 2012-06-28 2012-10-17 宁波君安药业科技有限公司 Method and device for identifying radionuclide Sr-89 and analyzing nuclear purity
CN107076860A (en) * 2014-05-28 2017-08-18 索列丹斯弗莱西奈公司 Radioactive material is determined
CN107076860B (en) * 2014-05-28 2020-03-10 索列丹斯弗莱西奈公司 Radioactive material assay
CN111999763A (en) * 2020-08-26 2020-11-27 山西医科大学 Accommodating device, activity detection station and activity detection method
CN111999763B (en) * 2020-08-26 2022-12-30 山西医科大学 Accommodating device, activity detection station and activity detection method

Similar Documents

Publication Publication Date Title
CN102736098A (en) Method and device for identifying radionuclide Sr-89 and analyzing nuclear purity
CN102621588B (en) Gamma energy spectrum-based method for identifying clay shale reservoir and uranium ore occurrence on spot
Samsahl et al. Automatic group separation system for the simulataneous determination of a great number of elements in biological material of a great number of elements in biological material. Recovery and reproducibility studies
CN108152846A (en) A kind of digitalization radiation inert gas133Xe activity coincidence measurement devices
CN202676922U (en) Rapid discriminating and nuclear purity analysis apparatus of radionuclide Sr-89
CN209560093U (en) The fast automatic analytical equipment of tritium in water
Cantaluppi et al. Methods for radioactivity measurements in drinking water using gamma spectrometry
CN209674006U (en) A kind of verification body source device of uranium ore radioactivity survey instrument
Forte et al. Natural radionuclides measurements in drinking water by liquid scintillation counting. methods and results
Brown et al. Ge (Li)–Ge (Li) gamma-ray coincidence studies of the decay of 18.6 h 159Gd
CN103424767A (en) Method for measuring content of 235U and 239Pu in U-Pu mixture
Zhang et al. In situ experimental measurement of mercury by combining PGNAA and characteristic X-ray fluorescence
CN202003031U (en) Radionuclidic iodine-125 nuclear-purity rapid measuring device
Piepke et al. A method to calibrate a neutrino detector using the positron emitter 68Ge
Kusaka et al. Non-destructive determination of chlorine in organic compounds by neutron-capture gamma-ray measurement, using an isotopic neutron source
Haddad et al. Volume efficiency correction factor determination for gamma spectrometry using 82 Br
Butkalyuk et al. Rapid determination of strontium-90 in seawater
HILA et al. The potential of an unused Pu-Be isotopic neutron source for detection of gold by neutron activation analysis
Yuguang et al. Determination of rare earths and other trace elements in samples of Antarctica by neutron activation analysis
Wores ELEMENTAL ANALYSIS OF GEOLOGICAL, HERBAL AND FOOD SAMPLES USING INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS (INAA)
Ruskov et al. Prompt Gamma Emission in Resonance Neutron Induced Fission of 239Pu
De Lange The determination of uranium and thorium in urano-thorianite and monazite by the" Equlibrium" method
CN116106346A (en) Seawater in-situ gamma energy spectrum efficiency calibration method
Szegedi et al. Determination of oxygen in rock samples by fast-neutron activation
Reeder et al. Moisture measurement for radioactive wastes using neutron activation of copper

Legal Events

Date Code Title Description
C14 Grant of patent or utility model
GR01 Patent grant
CX01 Expiry of patent term
CX01 Expiry of patent term

Granted publication date: 20130116