阅读说明：本技术 一种核素治疗病人的出入通道及路径设计方法 (Entry and exit channel and path design method for nuclide treatment patient ) 是由 邓贞宙 赖文升 周凯 于 2020-05-28 设计创作，主要内容包括：本发明提供一种核素治疗病人的出入通道及路径设计方法,其中装置和模块包括热释光个人剂量计(TLD)连接医护人员的不同部位,测其累积剂量当量；活性加速器与同位素示踪剂剂量连接,生产病患所需的药物；射线检测仪与病人连接,测量出病人体内残余辐射剂量。该装置可以有效减少医疗工作人员和无关人员受到核素的辐射,也能相应的减少医院的医疗成本。(The invention provides an access passage and a path design method for nuclide treatment patients, wherein a device and a module comprise thermoluminescent personal dosimeters (TLDs) which are connected with different parts of medical care personnel and used for measuring the equivalent cumulative dose; the active accelerator is connected with the dosage of the isotope tracer to produce the medicine needed by the patient; the radiation detector is connected with the patient and is used for measuring the residual radiation dose in the patient. The device can effectively reduce the radiation of nuclides to medical staff and irrelevant staff, and can correspondingly reduce the medical cost of hospitals.)

1. An access channel for nuclide therapy to a patient, comprising: the injection chamber module is connected with the medicine production chamber module and is used for acquiring the isotope tracers produced by the active accelerator unit in the medicine production chamber module through the medicine conveying equipment unit; the injection room module is also connected with a rest room module and a detected room module; the examined room module is connected with the medicine producing room module and the waiting room module; the rest room module is connected with the thermoluminescent personal dosimeter module and the fine detection room module; the dose detection chamber module and the waiting chamber module are both connected with a hospital passageway.

2. The nuclide therapy patient access gateway as in claim 1, wherein the subject room module is provided with a PET detector unit and a radiation protection screen unit, and is equipped with a lead equivalent protective clothing.

3. The nuclide therapy patient access channel of claim 1, wherein a delivery conduit and a drug outlet are provided in the drug delivery device unit.

4. The nuclide therapy patient access gateway of claim 1, wherein the waiting room module comprises a stand-alone waiting room module and an intelligent timer.

5. A nuclide therapy patient access gateway as claimed in claim 1, wherein the rest module is provided with a self-contained rest room unit, the rest room unit 310 being provided with a self-disinfecting toilet and a water source.

6. The nuclear-treated patient doorway of claim 1 wherein the dose detection chamber module comprises a radiation detector unit 610, wherein the radiation detector unit 610 is configured to specifically detect ionizing radiation (X, α, β, γ) radiation by utilizing the penetrating power of X-rays, thereby efficiently detecting the residual radiation dose in the patient.

7. A nuclide therapy patient access port as in claim 1, wherein said thermoluminescent personal dosimeter is attached to a different site of a healthcare worker and its cumulative dose equivalent is measured.

8. A method of designing a path of an access channel for nuclide therapy to a patient as set forth in any one of claims 1 to 7 comprising the steps of:

step S1: determining a treatment area according to the surrounding environment, wherein the treatment area is far away from the crowd as far as possible, and if the condition is met, selecting an area shielded by walls, mountain bodies or trees;

step S2: determining the position of each department to ensure that the path from the beginning of examination to the last leaving of the patient is shortest;

step S3: diagnosing the patient to determine the drug required by the patient and the drug dose μ ═ kz3 λ 3;

step S4: determining the dosage of the isotope tracer and producing the isotope tracer tau (═ kizv) required for PET detection by an activity accelerator in a medicine producing room;

step S5: providing a safe and isolated injection environment for a patient in an injection room, and acquiring the isotope tracer produced by the active accelerator in the medicine production room through a pipeline by the injection room;

step S6: the rest room provides a rest place for the patient to promote the tracer to be distributed to the whole body, the rest room provides a separate isolated room, and a closestool is arranged in the isolated room;

step S7: the examined room is used for storing a PET detecting instrument, and the PET detecting instrument is used for treating the patient and isolating the pollution and the radiation source;

step S8: the patient waits in the waiting room for the reduction of the dosage of the radiopharmaceutical in the body and can leave the hospital after reaching the set standard;

step S9: the apparatus in the dose detection chamber will detect the dose level in the patient in a short time, when the dose is lower than the set dose, i.e. Δ D ═ 0.434 Δ t/(1+ n) ∈ (5.9 ± 1.1) mSv, the door is opened and the patient can pass; if the dosage is higher than the set dosage, the patient needs to return to a waiting room, and the patient waits for a period of time and then continues to carry out detection;

step S10: the patient leaving the treatment area will return to the original diagnosis room and be handed over to follow-up attention by a medical professional.

Technical Field

The invention relates to the field of path length design, patient excretion treatment, radiation isolation and drug radiation dose residue detection, in particular to an access channel for nuclide treatment patients and a path design method.

Background

Nuclear medicine imaging devices such as Positron Emission Tomography (PET) and single-photon emission computed tomography (SPECT) are important radiation sources for hospitals, including X-ray radiation generated by CT scan, which can be expressed by the formula N ═ N₀e^-λtAlso included are the gamma rays produced by the 18F-FDG drug during PET imaging, which can be represented by the formula I ═ I₀e^μtIndicating that the occurrence of radiation is still to be prevented within 10 half-lives of the subjects injecting the drug. In actual operation, should be based onThe physical characteristics of examinees are different, the dosage of the radiopharmaceuticals is reasonably selected, so that the irradiation dosage of the examinees is reduced as much as possible on the basis of obtaining qualified image images, and a safe and efficient examination path is needed to achieve the purposes of optimization and personalization. At present, in the aspect of nuclear PET and SPECT examination, the design specially aiming at the examination path is lacked. Except for the length of the examination path, the radiation isolation, the excretion treatment of patients, the site selection of the examination site and the detection of the residual radiation dose of the medicine are all included in the design range.

If the rough isolation mode and the examination path are adopted, the patient cannot be controlled and treated, but the condition of the patient may be aggravated, too much radiation is applied, the life is threatened, and even more, the patient may hurt medical care personnel or other innocent people. Therefore, designing an access channel and a path for nuclide treatment of a patient can have important influence on the PET treatment process.

Therefore, in view of the above technical problems, there is a need to provide a new approach for designing the access path and path of a patient treated with nuclides for PET treatment, so as to overcome the above drawbacks, achieve high-precision drug dosage control, reduce the radiation range, and reduce the path length during the patient detection process.

Disclosure of Invention

The invention aims to provide an access channel and a path design method for nuclide treatment patients, which can effectively prevent the patients and workers from being subjected to excessive radiation and provide a shortest, most comfortable and lowest-cost path for patient examination.

In order to solve the above technical problem, the present invention provides an apparatus, comprising: an injection room module 100, wherein the injection room module 100 is connected to the drug production room module 200 to provide a safe and isolated injection environment for the patient, and the injection room module 100 obtains the isotope tracer produced by the active accelerator unit 210 in the drug production room module 200 through the drug delivery equipment unit 110; the injection room module 100 is also connected with a rest room module 300;

the medicine producing room module 200 and the waiting room module 500 are connected to the examination room module 400; the examined room module 400 is connected with the injection room module 100; the injection room module 100 and the thermoluminescent personal dosimeter module 700 are connected with the rest room module 300; the rest room module 300 is connected with the dose detection room module 600; the waiting room module 500 and the dose detection room module 600 are connected with a hospital passageway;

the thermoluminescent personal dosimeter module 700 is connected with different parts of medical staff, the cumulative dose equivalent of the thermoluminescent personal dosimeter module is measured, and when the radiation cumulative dose equivalent is found to exceed the set equivalent, the medical staff needs to enter the rest room module 300 for disinfection until the cumulative dose equivalent is reduced to be lower than the set equivalent.

Wherein the active accelerator unit is adapted to be coupled to an isotopic tracer dosage for the production of a medicament for a patient.

Wherein, the delivery device unit 110 in the injection chamber module 100 comprises a delivery pipe 111 and a drug outlet 112, which is more convenient and sanitary.

The conveying pipeline 111 is made of a special material and used for isolating pollution and keeping the activity of the medicine, and the medicine outlet device 112 is connected with the conveying pipeline 111 and has strong isolation and accurate medicine dosage control;

wherein the restroom module 300 comprises a self-contained restroom unit 310, the restroom unit 310 being provided with a self-sanitizing toilet 311 and a water supply. The rest room module provides a rest place for the patient to promote the tracer to be distributed to the whole body, the rest room module provides a separate isolated room, and a closestool, a television and drinking water are arranged in the isolated room; the automatic disinfection type closestool can be fully automatically disinfected after being used, so that the excrement is prevented from further radiating the patient

Wherein, the examined room module 400 comprises a PET detector unit 420 and a radiation protection screen unit 410, and is equipped with lead equivalent protective clothing. The radiation-proof screen unit surrounds the PET detector unit and is used for weakening radiation emitted by the detector; the PET detection unit covers the whole examination process and is used for drug dose determination, time control and radiation determination which are all controlled by the system.

The waiting room module 500 includes an independent waiting room module 510 and an intelligent timer 511. The waiting room module is connected with the examined room module and the dose detection room module, and the patient can leave the hospital after the dose of the radiopharmaceutical in the patient is reduced. The intelligent timer is used for intelligently determining the waiting time of the patient and automatically reporting the time according to the injected dose and the received irradiation of the patient, so that the patient leaves the waiting room to go to the dose detection room for examination.

The dose detection chamber module 600 includes a radiation detector unit 610, and the radiation detector unit 610 is specifically a 451P radiation detector, and is configured to detect ionizing radiation (X, α, β, γ) rays specifically by using the penetrating ability of X rays, and efficiently detect the residual radiation dose in the patient. The detected data is output to the waiting room module. The dose detection unit detects the dose level in the patient in a relatively short time, below which the door opens and can be passed out of the hospital via the exit and above which it returns to the waiting room.

The invention provides a path design method of an access channel for nuclide therapy patients, which comprises the following steps:

step S1: determining a treatment area according to the surrounding environment, wherein the treatment area is far away from the crowd as far as possible, and if the condition is met, selecting an area shielded by walls, mountain bodies or trees;

step S2: determining the position of each department to ensure that the path from the beginning of examination to the last leaving of the patient is shortest;

step S3: diagnosing the patient to determine the drug required by the patient and the drug dose μ ═ kz3 λ 3;

step S4: determining the dosage of the isotope tracer and producing the isotope tracer tau (═ kizv) required for PET detection by an activity accelerator in a medicine producing room;

step S5: providing a safe and isolated injection environment for a patient in an injection room, and acquiring the isotope tracer produced by the active accelerator in the medicine production room through a pipeline by the injection room;

step S6: the rest room provides a rest place for the patient to promote the tracer to be distributed to the whole body, the rest room provides a separate isolated room, and a closestool is arranged in the isolated room;

step S7: the examined room is used for storing a PET detecting instrument, and the PET detecting instrument is used for treating the patient and isolating the pollution and the radiation source;

step S8: the patient waits in the waiting room for the reduction of the dosage of the radiopharmaceutical in the body and can leave the hospital after reaching the set standard;

step S9: the apparatus in the dose detection chamber will detect the dose level in the patient in a short time, when the dose is lower than the set dose, i.e. Δ D ═ 0.434 Δ t/(1+ n) ∈ (5.9 ± 1.1) mSv, the door is opened and the patient can pass; if the dosage is higher than the set dosage, the patient needs to return to a waiting room, and the patient waits for a period of time and then continues to carry out detection;

step S10: the patient leaving the treatment area will return to the original diagnosis room and be handed over to follow-up attention by a medical professional.

According to the technical scheme, the method for designing the access passage and the path of the nuclide treatment patient can effectively prevent the patient from being irradiated excessively, provides a shortest, most comfortable and lowest-cost path for the patient examination, and is particularly suitable for weak and older patients and hospitals with larger people flow.

The method for designing the access channel and the path of the nuclide treatment patient calculates the medicament dosage and the residual dosage in the body required by the patient through instruments such as a thermoluminescent personal dosimeter, an active accelerator and the like, has high accuracy, and injects the medicament dosage with high accuracy to the patient by adopting the most advanced cyclotron and the most reasonable tracer calculation method; the lead equivalent lead wall is used as a radiation isolation design, so that the radiation range is reduced, the radiation source is isolated, and the safety of patients and medical staff is guaranteed; the integrated design makes the system more compact, the processing flow is simple and clear, and the complexity is reduced.

Drawings

FIG. 1 is a flow chart of the method for designing the access and route of nuclide therapy patient according to the present invention

FIG. 2 is a plan view of the rest room of the present invention

FIG. 3 is a diagram of the design of the examined room of the present invention

FIG. 4 is a diagram of a waiting room according to the present invention

FIG. 5 is a diagram of an embodiment of the shortest path of the present invention

FIG. 6 is a schematic block diagram of the present invention, wherein 100 is an injector module; 110. a drug delivery device unit; 111. a delivery conduit; 112. a drug outlet; 200. a drug delivery chamber module; 210. an active accelerator unit; 300. a rest room module; 310. a separate lounge unit; 311. an automatic disinfection type toilet bowl; 400. a subject room module; 410. a radiation-proof screen unit; 420. a PET detection unit; 500. a waiting room module; 510. an independent waiting room module; 511. an intelligent timer; 600. a dose detection chamber module; 610. a radiation detector unit; 700. a thermoluminescent personal dosimeter module; 800. an ionization chamber patrol instrument module; 900. a path measurement device module.

The invention is further explained with reference to the drawings and the embodiments.

Detailed Description

The present invention will be further described with reference to the following specific examples. It should be understood that the following examples are illustrative only and are not intended to limit the scope of the present invention.

Fig. 1 is a schematic diagram of a patient access path according to an embodiment of the present invention, wherein a patient enters from an entrance door 1, arrives at a waiting room through a door 2 for a physical examination, then exits from a door 3 into the waiting room and then enters from a door 4 into a examined room, exits from a door 6 into the examined room after each basic examination of the body, enters from a door 7 into an injection room, exits from a door 8 after a nuclide is injected, enters from a door 10 into a rest room, waits for the decrease of the radiopharmaceutical dose in the body to reach a set standard, then exits from a door 11, enters into a nuclide dose detection room through a door 12, exits from a door 13 after the confirmation that the radiopharmaceutical dose in the body really reaches the set standard, and finally exits from a door 16 into the access path for nuclide treatment.

FIG. 3 is a schematic diagram of the structure of a subject chamber according to one embodiment of the present invention, in which the dose equivalent rate and distance correlation coefficient (r value) is-0.994, P < 0.05; the r-value of the dose equivalent rate and time is-0.988, P is less than 0.05, and the dose equivalent rate has better and negative correlation with distance and time. The time points at 1.0 and 1.5m from the subject were 342 and 266min, respectively, at a dose equivalent rate of 2.5 uLSv/h; the distance points 90 and 130min after injection of 18F-FDG were 3.9 and 3.4m, respectively. The PET scan conditions in this study were 120kVp, 220mAs, and the weighted CT dose index (CTDIW) was 24.3mGy, with an average injection of 18F-FDG 433MBq per subject for 1 PET examination. The literature reports that an average injection of 18F-FDG 370MBq per subject per PET examination, 18F-FDG, results in a dose equivalent of 7mSv, and scans result in a dose equivalent of 16.7-19.4 mSv. It can be seen that 18F-FDG causes less burden in the dose absorbed by the patient in the PCT/CT examination. From the perspective of radiation protection optimization, a physician should pay caution when applying for an examination, and fully consider the irradiation dose to which a subject is subjected during the examination; additionally, patients should be encouraged to accelerate the excretion of 18F-FDG for polydipsia, which is a simpler and feasible approach; the dosage should be regulated so as to reduce the dosage of 18F-FDG injection as much as possible.

When the treatment region is selected and the path is designed by using fig. 1, various factors should be considered, and the path design method of the access passage for nuclide treatment of a patient according to the invention should include the following steps:

step S1: determining a treatment area according to the surrounding environment, wherein the treatment area is far away from the crowd as far as possible, and if the condition is met, selecting an area shielded by walls, mountain bodies or trees;

step S2: determining the position of each department to ensure that the path from the beginning of examination to the last leaving of the patient is shortest;

step S3: diagnosing the patient to determine the drug and drug dosage required by the patient;

step S4: determining the dosage of the isotope tracer and producing the isotope tracer required by PET detection through an active accelerator in a medicine production room;

step S5: providing a safe and isolated injection environment for a patient in an injection room, and acquiring the isotope tracer produced by the active accelerator in the medicine production room through a pipeline by the injection room;

step S6: the rest room provides a rest place for the patient to promote the tracer to be distributed to the whole body, the rest room provides a separate isolated room, and a closestool is arranged in the isolated room;

step S7: the examined room is used for storing a PET detecting instrument, and the PET detecting instrument is used for treating the patient and isolating the pollution and the radiation source;

step S8: the patient waits in the waiting room for the reduction of the dosage of the radiopharmaceutical in the body and can leave the hospital after reaching the set standard;

step S9: the instrument in the dose detection chamber can detect the dose degree in the patient in a short time, and the door is opened when the dose is lower than the set dose, so that the patient can pass; if the dosage is higher than the set dosage, the patient needs to return to a waiting room, and the patient waits for a period of time and then continues to carry out detection;

step S10: the patient leaving the treatment area will return to the original diagnosis room and be handed over to follow-up attention by a medical professional.

According to one embodiment of the invention, the device is connected to a person to obtain the desired result, which will be used for the administration of a dose of medicament.

According to one embodiment of the invention, the connection of the modules will not have any place of communication with the hospital aisles.

According to an embodiment of the present invention, in the above step S4, the isotopic tracer is 18F fluorodeoxyglucose (18F-FDG) in this example.

According to an embodiment of the present invention, in the above step S4, the threshold value of the isotope tracer is set to be

According to an embodiment of the present invention, in step S5, the isolated room will use lead-equivalent lead walls as the isolation barrier.

According to an embodiment of the present invention, in step S9, the criterion is that the subject can leave the isolation region when the radiation dose is lower than the effective dose of (5.9 ± 1.1) mSv.

According to an embodiment of the present invention, in step S9, the apparatus for detecting dose is a 451P-ray detector.

According to one embodiment of the invention, the unit of the active accelerator in the medication chamber module is a MINItrac type active accelerator.

According to one embodiment of the invention, the individual waiting room modules employ lead equivalent lead walls as isolation barriers.

In the method for designing the access passage and the path of the nuclide treatment patient, the path length design refers to the distance from the patient to the injection chamber to the dose detection chamber.

In the method for designing the access channel and the path of the nuclide treatment patient, the 18F-FDG refers to fluorodeoxyglucose, the complete chemical name of which is 2-fluoro-2-deoxy-D-glucose, and is usually abbreviated as FDG, and the isotope tracer is adopted in the design method.

In the method for designing the access passage and the path of the nuclide treatment patient, the dosage detection refers to the detection used in the last step after the patient is treated by PET and waits for the medicine to be dissipated for a period of time in the design.

In the method for designing the access channel and the path of the nuclide treatment patient, the medicine producing room is a special place provided with a cyclotron.

Fig. 5 is a schematic diagram of an embodiment of the invention, our aim is to minimize the distance of the patient examination path, then Dijkstra's algorithm can be employed, which works by retaining the shortest path from s to v found so far for each vertex v. The steps of designing the access channel and path of nuclide treatment patient by using the method and the device are as follows:

step S1: the nodes in the graph are divided into 3 types: current vertex of the Current access; a point Fringe vertex that communicates with the current access node but has not been accessed; the Visited point Visited vertex;

step S2: starting from node A, the Fringe vertex of A is B and D (in the figure, inf represents infinite, which means that the path value from the current node to the target node is not yet known, and we set to infinity);

step S3: the path from the start node to the Fringe Vertex (startTofringe) is calculated as follows

startToFringe＝startToCurrent+currentToFringe；

Step S4: acquiring a path of the Fringe vertex in the note (Fringe InNoteDist);

step S5: finally, the value obtained in note is the shortest path from the starting point to the respective point.

FIG. 2 is a plan view of the lounge of the present invention; fig. 4 is a diagram of a waiting room design according to the present invention. The access channel and pathway design method for nuclide therapy patients according to the present invention will be further described by an embodiment in conjunction with fig. 1, 2 and 4. The invention provides a method for designing an access passage and a path of a nuclide treatment patient, which relates to the dosage of an isotope tracer 18F-FDG, wherein the dosage of the 18F-FDGPET imaging needs to be detected and evaluated according to an example, so that unnecessary radiation is avoided. The parameters of the application embodiments involved in processing the data are listed here.

According to one embodiment of the invention:

in the step (1), the medicine in the medicine producing chamber is conveyed by a medical pipeline, so that unnecessary contact and pollution are avoided.

The actual devices used in step (2) were Discovery VCT and MINItrac type cyclotrons. The estimation method of the internal irradiation dose comprises the following steps: the internal radiation dose to the examinee when the 18F-FDG PET/CT examination is carried out is generated by positron annihilation radiation, and the effective dose can be calculated according to the radioactivity: e ═ Sigma eq ^ o (\ s \ do4(T)) WT & DT or E ═ A · ^ Sigma eq ^ o (\ s \ do4(T)) WT & TEDG or E ═ A & EFDG. Wherein A represents the radioactivity of the injected 18F-FDG in MBq or mCi, and EEDG and TEDG represent the injection activity and absorbed dose conversion coefficient of different age individuals and different organs, respectively, as recommended in International Commission on Radioactive Protection (ICRP) publication No. 106 in mGy/MBq; WT refers to the weight factor of different organs. CT scanning is performed first, PET 3D scanning is performed immediately, 6-8 window levels are provided, each window level is 15.7cm, and the scanning time is 2 min.

And (3) estimating the CT radiation dose. There are 2 general methods for calculating CT radiation dose: the 1 st is that the whole body dose conversion coefficient is calculated according to 0.015 mSv/(mGy. cm); species 2 were calculated for the head, neck, chest, abdomen and pelvic regions, respectively, and their respective conversion factors were 0.0021, 0.0059, 0.014, 0.015 and 0.015 mSv/(mGy. cm), respectively, according to ICRP publication No. 102. The calculation formula is as follows: ECT K CDTIvol LR ·ΣWR or ECT K DLPR ∑ WR, where K is a conversion coefficient between different individuals; CTDIvol represents volumetric CT dose index (volume CTdose index); LR is the scan length of different parts of the body along the z-axis; WR is the dose effect conversion coefficient of different parts of human body; the Dose Length Product (DLP) is obtained by multiplying the CTDIvol by the scan length.

And (4) after the injection is finished, ordering the patient to rest, drinking 600ml, emptying urine after 45min, and quickly drinking 100 ml and 200 ml. The tube voltage is 120kV, the current is 60-180mAs, and the layer thickness is 3.75mm by using an automatic exposure technology.

And (5) preparing trained medical personnel to carry out PET/CT scanning detection on the patient, wherein the patient needs to wear a lead garment with lead equivalent of 0.5 mm.

Step (6) and the rest room after injection are the same, an independent small room is designed to provide a seat for a patient to rest, an independent closestool is provided to prevent urine from radiating to other patients, and drinking water can be independently provided.

Step (7) will measure the radiation dose using a 451P radiation detector.

The method can be used for radiation protection isolation technology, including nuclide injection, nuclear radiation time measurement, nuclear medicine instruments and shortest path design.

The invention provides an access channel and a path design method for nuclide therapy patients. The lead equivalent lead wall effectively isolates the drug radiation and reduces the harm to the minimum. The lead screen with the lead equivalent of 8mm and the lead clothes with the lead equivalent of 0.5mm are used as protective articles, so that safety guarantee can be provided for patients, medical staff and external staff of hospitals. The radiation dosage is measured by the ray detector unit, so that the radiation of residual medicines in the body of a patient can be more effectively detected.

By adopting the design method of the access passage and the path of the nuclide treatment patient, the nuclide treatment patient can effectively avoid the patient from being irradiated excessively, provides a shortest, most comfortable and lowest-cost path for the patient examination, and is particularly suitable for weak and older patients and hospitals with larger people flow.

The method for designing the access channel and the path of the nuclide treatment patient calculates the medicament dosage and the residual dosage in the body required by the patient through instruments such as a thermoluminescent personal dosimeter, a MINITrac type active accelerator and the like, has high accuracy, and adopts the most advanced cyclotron and the most reasonable tracer calculation method to inject the medicament dosage with high accuracy into the patient; the lead equivalent lead wall is used as a radiation isolation design, so that the radiation range is reduced, the radiation source is isolated, and the safety of patients and medical staff is guaranteed; the integrated design makes the system more compact, the processing flow is simple and clear, and the complexity is reduced.

Positron emission tomography imaging is collectively referred to as: positron emission computed Tomography (PET for short) is an advanced clinical examination imaging technology in the field of nuclear medicine.

Single photon emission computed tomography is a CT technique for nuclear medicine that images gamma rays emitted from within a patient.

Ct (computed tomography), namely, computed tomography, which uses precisely collimated X-ray beams, gamma rays, ultrasonic waves, etc. to scan sections of a human body one after another around a certain part of the human body together with a detector with extremely high sensitivity, has the characteristics of fast scanning time, clear images, etc., and can be used for the examination of various diseases; the following can be classified according to the radiation used: x-ray CT (X-CT), ultrasonic CT (uct), and gamma-ray CT (gamma-CT), etc.

18F-FDG (18F fluorodeoxyglucose) is a chemical substance with the molecular formula CB 2154354.

A thermoluminescent personal dosimeter is a device that uses the thermoluminescent principle to record the cumulative radiation dose.

Isotopic tracers are also known as isotopic indicators (isotopic indicators), isotopic labels (isotopic labels), and labels (labels). The tracer, which is incorporated in small amounts into a sample (carrier) of the same labelled element but of a different isotopic composition or energy state, is intended to trace the pathway which this element undergoes in a certain chemical, biological or physical process, and in fact the sample.

Lead equivalent: in order to compare the shielding performance of various shielding materials, the thickness of a lead layer that achieves the same shielding effect as a certain thickness of a shielding material is generally referred to as the lead equivalent of the shielding material with lead as a reference. The attenuation equivalent expressed in terms of the thickness of lead when lead is used as a reference substance.

The CT dose index (CTDIW) is the integral of the vertical line dose distribution from-50 mm to plus +50mm along the slice plane generated for one single axial scan.

Dijkstra (Dijkstra) algorithm was proposed by the netherlands computer scientist dickstra in 1959, and is therefore also called dickstra algorithm. The method is a shortest path algorithm from one vertex to the rest of the vertices, and solves the shortest path problem in the directed graph. The Dijkstra algorithm is mainly characterized in that the Dijkstra algorithm expands outwards layer by taking a starting point as a center until the expansion reaches a terminal point.

The above embodiments are merely preferred embodiments of the present invention, which are not intended to limit the scope of the present invention, and various changes may be made in the above embodiments of the present invention. All simple and equivalent changes and modifications made according to the claims and the content of the specification of the present application fall within the scope of the claims of the present patent application. The invention has not been described in detail in order to avoid obscuring the invention.