CN106581873B - Method for detecting radioactive dose - Google Patents
Method for detecting radioactive dose Download PDFInfo
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- CN106581873B CN106581873B CN201611119569.5A CN201611119569A CN106581873B CN 106581873 B CN106581873 B CN 106581873B CN 201611119569 A CN201611119569 A CN 201611119569A CN 106581873 B CN106581873 B CN 106581873B
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
- A61N5/1071—Monitoring, verifying, controlling systems and methods for verifying the dose delivered by the treatment plan
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Abstract
The invention relates to the technical field of medical treatment and discloses a radioactive dose detection method. The radioactive dose detection method includes the steps of: acquiring a three-dimensional model of a filler of a part to be irradiated of a patient; setting an accommodating space in the obtained three-dimensional model; printing by using a 3D printer to obtain an entity of the filling; placing a dose detector in the accommodating space of the entity; placing the entity into a part to be irradiated of a patient, and radiating the part to be irradiated; the dose detector is removed and the amount of radioactive dose absorbed by the dose detector is detected. The detection method can accurately detect the radioactive dose of the irradiated part of the patient ray in a human body.
Description
Technical Field
The invention relates to the field of medical instruments, in particular to a radioactive dose detection method.
Background
Radiation therapy, or combination therapies based on radiation therapy, is the most commonly preferred treatment option in the medical field today for tumor therapy. Among them, more than 70% of head and neck tumors require radiotherapy intervention.
In the radiation treatment process, the radioactive dose of the patient affected part is accurately detected, and the treatment accuracy can be effectively improved. The conventional radioactive dose detection method is generally to place a radioactive dose detector on the surface of a patient and determine the dose of radiation irradiated to the human body by detecting the dose of radiation absorbed.
However, the inventors of the present invention have found that the prior art has several problems, namely, the radioactive dose detector is fixed on the surface of the patient, and only reflects the radioactive dose of the radiation on the surface of the patient, and for the case that the affected part is located inside the body such as uterus and liver, the radioactive dose detector cannot truly reflect the dose distribution of the radiation on the specific affected part of the patient; in addition, the radioactive dose detector is fixed on the surface of a patient, so that the implementation is inconvenient, and the detector is easy to shake due to the movement of the patient body, so that the accuracy of a detection result is directly influenced; thirdly, if the radioactive dose detector is placed inside the body, it is easily affected by the ph value in the body or rejection occurs, directly affecting the detection result of the radioactive dose detector.
Disclosure of Invention
The present invention has an object to provide a radioactive dose detection method which can accurately detect the radioactive dose of a radiation-irradiated site of a patient.
In order to solve the above technical problem, an embodiment of the present invention provides a radioactive dose detection method, including the steps of:
acquiring a three-dimensional model of a filler of a part to be irradiated of a patient; setting an accommodating space in the obtained three-dimensional model; printing and obtaining an entity of the filling material by using a 3D printer; placing a dose detector in the accommodating space of the entity; placing the entity into a part to be irradiated of a patient, and irradiating the part to be irradiated; and taking out the dose detector, and detecting the radioactive dose absorbed by the dose detector.
The embodiment of the invention also provides a radioactive dose detection device, and radioactive dose detection is carried out by using the method. Comprises a filler, is used for filling the part to be irradiated of a patient, and is internally provided with an accommodating space; the radioactive dose detection device further comprises N dose detectors, the dose detectors are arranged in the accommodating space, and N is a natural number.
Compared with the prior art, the dose detector is arranged in the solid body of the filling material, so that the dose detector can be arranged at the part to be irradiated (such as cervix, oral cavity, nasal cavity, esophagus and other cavities in the body) of the patient, and compared with the mode that the dose detector can only be arranged on the body surface of the patient in the prior art, the part capable of detecting the radioactive dose is greatly expanded, and the detection of the radioactive dose is more accurate. In addition, because the dose detector is arranged in the body of the patient, the detection result can reflect the distribution of the radioactive dose of a specific diseased part of the patient, and the obtained radioactive dose distribution result is helpful for a doctor to carry out individual analysis and provides a quantitative basis for the doctor to formulate the subsequent radioactive treatment.
Preferably, the number of the dose detectors is N, where N is a natural number greater than or equal to 2, and the step of placing the dose detectors in the accommodating space of the entity further includes the following sub-steps: and uniformly distributing the dose detector in the accommodating space along the irradiation direction of the rays. The plurality of dose detectors are arranged in the radiation direction, so that the dose detectors can absorb the radiation in the radiation direction, and the radioactive dose detected by the dose detectors can reflect the radiation dose of the radiation irradiation part more truly.
Preferably, the number of the dose detectors is N, where N is a natural number greater than or equal to 4, and the step of placing the dose detectors in the accommodating space of the entity further includes the following sub-steps:
the dose detectors are divided into two groups, wherein one group is uniformly distributed in the accommodating space along the irradiation direction of the rays, and the other group is staggered with the irradiation direction of the rays and is uniformly distributed in the accommodating space. The embodiment of the invention uniformly arranges the dose detectors in two directions, can analyze the dose distribution of the primary ray irradiated on the plane formed by the two groups of detectors, and further improves the reliability of the detection result of the dose detectors.
Preferably, the dose detector is a thermoluminescent or photoluminescent detector. The detector has the advantages of small volume, good energy response, high sensitivity, convenient use and capability of measuring various rays such as alpha, beta, gamma, X, n and the like. Compared with the commonly adopted methods such as an ionization chamber or a film, the method also has the advantages of good tissue equivalence, capability of measuring the accumulated dose in a longer time, stable performance and the like.
Preferably, the accommodating space comprises at least one passage penetrating through the filler, and the dose detectors are arranged in the passage at intervals. According to the embodiment of the invention, the dose detector is placed in the channel of the accommodating space, so that the ray dose distribution in one direction can be detected.
Preferably, the channels are two and the two channels are interleaved. Two channels are arranged and staggered with each other, and the dose detector can be placed at different positions through different channels so as to further detect radioactive doses in two directions.
Preferably, the radioactive dose detection apparatus further comprises guide tubes, the dose detectors being arranged at intervals in the guide tubes, the guide tubes penetrating into the passage. The guide pipe is arranged, so that the dose detector can be guided to different positions in the accommodating space through the channel, and the dose detector is quicker and more convenient to use.
Preferably, the radioactive dose detection apparatus further comprises at least H barriers, said H being greater than or equal to N-1 and less than or equal to N + 1; wherein each dose detector and each barrier are alternately arranged in sequence within the guide tube. The blocking piece is arranged to support the guide tube on one hand, and on the other hand, the dose detector can be guaranteed to be uniformly distributed in the accommodating cavity so as to detect the ray doses of different parts.
Drawings
Fig. 1 is a flowchart of a radioactive dose detection method according to a first embodiment of the present invention;
fig. 2 is a schematic model diagram of a filling in a radioactive dose detection apparatus according to a second embodiment of the present invention;
fig. 3 is an intra-tube schematic view of a guide tube in a radioactive dose detection apparatus according to a second embodiment of the present invention;
FIG. 4 is a schematic view of the guide tube being placed in the receiving space of the filler;
FIG. 5 is a schematic view of a receiving space with two channels according to a second embodiment of the present invention;
fig. 6 is a schematic view of a guide tube in a third embodiment according to the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail below with reference to the accompanying drawings. However, it will be appreciated by those of ordinary skill in the art that numerous technical details are set forth in order to provide a better understanding of the present application in various embodiments of the present invention. However, the technical solutions claimed in the claims of the present application can be implemented without these technical details and with various changes and modifications based on the following embodiments.
A first embodiment of the present invention relates to a radioactive dose detection method with which the radioactive dose of a radiation-irradiated site of a patient can be accurately reflected. As shown in the flowchart 1, the following is specifically introduced:
step 101: a three-dimensional model of a filling of a region to be irradiated of a patient is acquired.
For a more clear description of the specific implementation of this step, the affected area is taken as the oral cavity, and the filling is a mouthpiece.
Those skilled in the art will appreciate that there are various ways to obtain a three-dimensional model of the filling of the oral cavity of a patient, and the present embodiment obtains a model of the oral cavity of a patient as follows:
firstly, taking a proper amount of impression paste according to the mouth opening degree of a patient, placing the impression paste in hot water of 70 ℃ for soaking for 2-3 minutes, stirring materials in the hot water to mix the impression paste preliminarily after the impression paste is melted, fishing out melted soft impression paste lumps from the water by wearing rubber gloves, placing the soft impression paste lumps in palms, kneading and extruding large bubbles in the paste, simultaneously enabling the surfaces of the soft impression paste lumps to be smoother, shaping the front end of the impression paste by using the mouth of a hand of an operator, and enabling the front end of a die body to be suitable for the radian of the front end of an occlusal surface of the patient; then, advising the patient to open the mouth, holding the impression paste die body from the front to the back, visually observing the upper and lower opening degrees on the occlusion plane of the patient, and extruding the die body up and down to ensure that the upper and lower heights of the die body are as less as possible and close to the opening degree of the patient;
then vertically placing the die body of the impression paste at the lower part of the lower lip of the patient to ensure that the central line of the die body is superposed with the human body central line of the coronal plane of the patient as much as possible, advising the patient to open the mouth, directly viewing the width between the left and right lower molars of the patient, and correcting the left and right width at the rear part of the die body to ensure that the width is slightly larger than the width between the left and right molars of the patient;
then, after the die body is shaped, advising the patient to open the mouth and place the tongue below the die body as much as possible, and slowly placing the die body in the mouth of the patient from the front to the back direction on the occlusion plane of the patient, so as to avoid the situation that the teeth touch the die body during opening the mouth to cause deformation beyond the expectation, and the patient is noticed whether the accidental situations such as nausea and the like occur or not and the situations which need stopping possibly occur;
the die body is properly placed, the rear part of the die body is placed at the first molar part at least, the rear boundary of the die body can be placed at the level of the second molar part and the third molar part of the cross section, but nausea symptoms can be caused by excessive penetration into the oral cavity and contact and pressure on receptors such as a tongue, the tolerance level of different patients is different, and the level of less occurrence of nausea symptoms is observed by the current practice that the rear boundary of the die body is placed at the first molar part;
after the mold body is properly placed, guiding the patient to do occlusion action, but not applying too much force to avoid biting through the mold body, ordering the patient to open the mouth for 10 to 20 seconds, and slowly taking out the mold body with the tooth mark; washing the die body with cold water and cooling for about 1 minute, wherein the die body has hard surface touch and is taken out after the shape is fixed; checking the surface of the mold body and the extracted tooth marks, putting the mold body into the mouth of the patient again after determining that the tooth marks are correct, taking out the mold body after determining that the upper jaw and the lower jaw are fixed accurately, cleaning and airing for later use.
It should be noted that, as will be understood by those skilled in the art, when the step is implemented in detail, the three-dimensional model of the filling material of the to-be-irradiated portion may be obtained in other manners, and the embodiment is not limited thereto.
Step 102: and setting an accommodating space in the obtained three-dimensional model.
Specifically, in the three-dimensional model obtained above, an accommodating space is provided for subsequently placing the dose detector. For example, in combination with the oral cavity, the accommodating space may be provided in the obtained oral cavity mold body in the following manner.
Firstly, placing a mold body with imprints of upper and lower jaw teeth of a patient on a CT bed, placing rectangular plastic foam as a placing platform, placing a long shaft of the mold body on a shaft of a bed feeding direction of the CT scanning bed, opening CT laser and the like, adjusting the height and the inlet and outlet of the bed plate, and placing a central focus of a laser line at the center of the mold body approximately;
after the scanning is finished, the generated DICOM image file is transmitted to an MIM planning system by a GE image workstation AW 4.2; finding out a specific DICOM folder from the MIM software file receiving and storing set, and copying the specific DICOM folder to a mobile storage;
opening a die body image file in a mobile storage by using a mix software, taking the approximate center of the internal partial volume of a die body opening, making a straight line on a sagittal plane, and making a cylinder with the diameter of 6mm (or setting the specific size according to the requirement) by taking the straight line as a central axis; the model with a hollow cylindrical containing space is obtained by subtracting the cylinder from the module function of the drawing software.
Step 103: and printing and obtaining the solid of the filling material by using a 3D printer.
Generally, the process of printing out an entity in a 3D mode after computer modeling only needs 1 to 2 hours, the printing equipment occupies a small space, printing can be directly realized in a hospital, the time spent in circulation is further reduced, and the working efficiency of doctors is improved. In addition, the printed mold body needs to be cleaned in the accommodating space, and redundant printing materials in the mold body are removed.
It will be appreciated by those skilled in the art that the 3D printed material that may be used in embodiments of the present invention includes a variety of materials. Due to the outstanding advantages of the high polymer material in the aspects of cost, plasticity, biocompatibility and the like, the printed finished product has uniform density and is degradable, and the high polymer material is beneficial to environmental protection and becomes a preferred material for the oral cavity model.
Step 104: a dose detector is placed in the accommodating space of the solid body.
The number of the dose detectors may be N, where N is a natural number greater than or equal to 2, and in the step of placing the dose detectors in the accommodating space of the entity, the following substeps may be further included: and uniformly distributing the dose detector in the accommodating space along the irradiation direction of the ray. The plurality of dose detectors are arranged in the radiation direction, so that the dose detectors can absorb the radiation in the radiation direction, and the radioactive dose detected by the dose detectors can reflect the radiation dose of the radiation irradiation part more truly.
As a further improvement, the number of the dose detectors is N, where N is a natural number greater than or equal to 4, and in the step of placing the dose detectors in the accommodating space of the entity, the sub-step further includes: the dose detectors are divided into two groups, wherein one group is uniformly distributed in the accommodating space along the irradiation direction of the rays, and the other group is staggered with the irradiation direction of the rays and is uniformly distributed in the accommodating space.
It should be noted that the two groups of dose detectors may be arranged to be perpendicular to each other, that is, one group of dose detectors is uniformly distributed in the accommodating space along the irradiation direction of the radiation, and the other group of dose detectors is perpendicular to the irradiation direction of the radiation and is uniformly distributed in the accommodating space.
Step 105: the entity is placed in the part to be irradiated of the patient, and the part to be irradiated is radiated.
After the dose detector is placed in the containing space of the neck mold, the entity of the neck mold is placed in the part to be irradiated of the patient, and the part to be irradiated is radiated.
Step 106: the dose detector is removed and the amount of radioactive dose absorbed by the dose detector is detected.
After the radiation is completed, the filling material is taken out of the patient affected part, the dose detector is taken out, and the amount of the radiation absorbed by the dose detector is detected to reflect the amount of the radiation at the patient affected part.
Those skilled in the art will appreciate that the dose line range can be obtained through simulation calculation of a CMS or pinnalle radiotherapy planning system, and the experimental design is compared with the dose line range according to the TLD set in the accommodating space, where the possible comparison situations include 1, with dose and without dose; 2. high and low doses; 3. comparison within the range of equivalent dosages.
Compared with the prior art, in the embodiment, the three-dimensional model of the filling material of the part to be irradiated of the patient is firstly obtained, the accommodating space is arranged in the three-dimensional model, the solid is printed out by using the 3D printing technology, and the dose detector is arranged in the solid of the filling material, so that the dose detector can be arranged in the part to be irradiated of the patient (the oral cavity in the embodiment, actually other cavities such as cervix, nasal cavity, esophagus and the like which are positioned in the body), compared with the mode that the dose detector can only be arranged on the body surface of the patient in the prior art, the part capable of detecting the radioactive dose is greatly expanded, and the detection of the radioactive dose is more accurate. In addition, because the dose detector is arranged in the body of the patient, the detection result can reflect the distribution of the radioactive dose of a specific diseased part of the patient, and the obtained radioactive dose distribution result is helpful for a doctor to carry out individual analysis and provides a quantitative basis for the doctor to formulate the subsequent radioactive treatment.
A second embodiment of the present invention relates to a radioactive dose detection apparatus for detecting a radioactive dose of a specific radiation irradiation site of a patient by the method of the first embodiment. Referring to fig. 2, in the present embodiment, the radiation treatment device includes a filler 200 for filling a portion to be irradiated of a patient, and an accommodating space 201 is preset in the filler; the radioactive dose detection device further comprises N dose detectors, the dose detectors are arranged in the accommodating space, and N is a natural number.
The accommodating space may be disposed at a central position in the filler 200, or may be disposed at other positions as needed, which is not specifically limited in this embodiment. In addition, the size of the accommodating space 201 can be determined according to the number of dose detectors to be placed, the shape of the accommodating space can be cylindrical, elliptical or other shapes, etc., the accommodating space in this embodiment can be a channel penetrating through the filling, the channel 201 can be a cylindrical channel or a channel with other shapes, and the channel is preferably a straight channel. The channels of the receiving space are arranged along the radiation direction 205, and the radiation dose distribution in one direction can be detected by placing the dose detector in the channels of the receiving space.
It should be noted that, in order to guide the dose detector to different positions in the accommodating space through the channel more quickly and conveniently, the radioactive dose detection apparatus of the present embodiment may further include a guide tube 204, which penetrates into the channel 201. In addition, as a further improvement, at least H barriers 203 may be provided in the guide tube 204, H being greater than or equal to N-1 and less than or equal to N + 1; wherein each dose detector 202 and each blocking member 203 are alternately arranged in turn in the guide tube 204. The blocking member 203 is arranged to support the guiding tube 204, and to ensure that the dose detector 202 is uniformly distributed in the accommodating cavity to detect the radiation dose at different positions. Fig. 4 is a schematic view of the guide tube 204 being placed in the accommodating space channel.
In the embodiment of the invention, the dose detector is a thermoluminescent detector. The pyroelectric detector has the advantages of small volume, good energy response, high sensitivity, convenient use and capability of measuring a plurality of rays such as alpha, beta, gamma, X, n and the like. Compared with the commonly adopted methods such as an ionization chamber or a film, the method also has the advantages of good tissue equivalence, capability of measuring the accumulated dose in a longer time, stable performance and the like.
As a further improvement, as shown in fig. 5, two channels may be provided in the accommodating space, and the two channels are staggered with each other, i.e., fig. 201 and 206. Two channels are arranged and staggered with each other, and the dose detector can be placed at different positions through different channels so as to further detect radioactive doses in two directions. By detecting the radioactive dose in two directions, the radioactive dose of the radiation irradiation portion can be reflected more truly.
It should be noted that, in order to achieve a better detection effect, the two channels 201 and 206 may be disposed in a mutually perpendicular manner, that is, the channel 201 is disposed along the radiation direction, the channel 206 is disposed in a direction perpendicular to the radiation direction, and the dose detector is disposed in the two channels, so that a dose distribution of radiation on a plane formed by the two sets of detectors can be analyzed, and the reliability of the detection result of the dose detector is further improved.
Since this embodiment is a system example corresponding to the first embodiment, this embodiment can be implemented in cooperation with the first embodiment. The related technical details mentioned in the first embodiment are still valid in this embodiment, and the technical effects that can be achieved in the first embodiment can also be achieved in this embodiment, and are not described herein again in order to reduce the repetition. Accordingly, the related-art details mentioned in the present embodiment can also be applied to the first embodiment.
A third embodiment of the present invention relates to a radioactive dose detection apparatus, and differs from the second embodiment mainly in that: the guide tube 204 is of a different construction. In the second embodiment, the guide tube 204 is a hollow body structure, and a blocking member and a dose detector are arranged inside the hollow body structure; in the present embodiment, the guide tube 204 is a solid body structure, and a slot is provided at an outer surface of the solid body.
Referring to fig. 6, the guide tube 204 in this embodiment is a solid structure, N slots are embedded in the surface of the cylindrical solid structure, and the dose detector 202 is disposed in the slots. The guide tube 204 is disposed in the housing space, and the radioactive dose distribution at the radiation irradiation site can be detected.
It will be understood by those of ordinary skill in the art that the foregoing embodiments are specific examples for carrying out the invention, and that various changes in form and details may be made therein without departing from the spirit and scope of the invention in practice.
Claims (3)
1. A radioactive dose detection method characterized by: the method comprises the following steps:
acquiring a three-dimensional model of a filler of a part to be irradiated of a patient;
setting an accommodating space in the obtained three-dimensional model;
printing and obtaining an entity of the filling material by using a 3D printer;
placing a dose detector in the accommodating space of the entity;
placing the entity into a part to be irradiated of a patient, and irradiating the part to be irradiated;
and taking out the dose detector, and detecting the radioactive dose absorbed by the dose detector.
2. The radioactive dose detection method according to claim 1, wherein: the number of the dose detectors is N, wherein N is a natural number greater than or equal to 2, and in the step of placing the dose detectors in the accommodating space of the entity, the sub-steps of:
and uniformly distributing the dose detector in the accommodating space along the irradiation direction of the ray.
3. The radioactive dose detection method according to claim 1, wherein: the number of the dose detectors is N, wherein N is a natural number greater than or equal to 4, and the step of placing the dose detectors in the accommodating space of the entity further comprises the following substeps:
dividing the dose detectors into two groups, wherein one group is uniformly distributed in the accommodating space along the irradiation direction of the rays, and the other group is staggered with the irradiation direction of the rays and is uniformly distributed in the accommodating space.
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| CN201611119569.5A CN106581873B (en) | 2016-12-07 | 2016-12-07 | Method for detecting radioactive dose |
| CN201910521744.0A CN110354403B (en) | 2016-12-07 | 2016-12-07 | Radioactive dose detection device |
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| CN201611119569.5A CN106581873B (en) | 2016-12-07 | 2016-12-07 | Method for detecting radioactive dose |
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| CN108888875A (en) * | 2018-06-28 | 2018-11-27 | 广州医科大学附属肿瘤医院 | A kind of body irradiation tissue compensation device and preparation method thereof |
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| CN2298569Y (en) * | 1997-05-04 | 1998-11-25 | 四川联合大学人机科学与工程中心 | Model for human pars nasalis pharyngis radiation, diagmose and treatment |
| CN2369254Y (en) * | 1999-01-06 | 2000-03-15 | 北京放射医学研究所 | Infrared personal meter |
| WO2003062855A1 (en) * | 2002-01-25 | 2003-07-31 | University Of Wollongong | Method and apparatus for real time dosimetry |
| US7354391B2 (en) * | 2003-11-07 | 2008-04-08 | Cytyc Corporation | Implantable radiotherapy/brachytherapy radiation detecting apparatus and methods |
| US20060027756A1 (en) * | 2004-08-09 | 2006-02-09 | Ian Thomson | Dosimeter having an array of sensors for measuring ionizing radiation, and dosimetry system and method using such a dosimeter |
| EP1951372A4 (en) * | 2005-11-15 | 2011-06-22 | Neovista Inc | Methods and apparatus for intraocular brachytherapy |
| JP2009524835A (en) * | 2006-01-30 | 2009-07-02 | ザ ユニバーシティ オブ シドニー | Fiber optic dosimeter |
| JP2010256176A (en) * | 2009-04-24 | 2010-11-11 | Toshiba Corp | Nuclear medicine diagnosis system, and administration dose calculation method of the same |
| CN102033239B (en) * | 2009-09-28 | 2013-07-10 | 同方威视技术股份有限公司 | X-ray energy measuring system for accelerator |
| CN101831702B (en) * | 2010-05-21 | 2012-05-23 | 中国科学院上海光学精密机械研究所 | Copper-doped yttrium aluminate crystal for thermoluminescence and photoluminescence and preparation method thereof |
| CN202066972U (en) * | 2011-03-04 | 2011-12-07 | 中国原子能科学研究院 | Personal neutron dosimeter with energy compensation |
| CN102967872A (en) * | 2011-08-31 | 2013-03-13 | 曹暾 | Body cavity inner dose detector integrated in brachytherapy system |
| CN102551784B (en) * | 2012-03-06 | 2014-05-07 | 中国科学院高能物理研究所 | Dedicated breast phantom of CT equipment for breast |
| CN102727239B (en) * | 2012-07-06 | 2014-01-08 | 中国科学院高能物理研究所 | Mammary gland die body with chest wall radiation dose measurement function |
| CN103472476B (en) * | 2013-09-16 | 2015-09-30 | 中国船舶重工集团公司第七一九研究所 | A kind of detector for environmental radiation dose rate monitoring |
| CN204790010U (en) * | 2015-06-01 | 2015-11-18 | 中国计量科学研究院 | Irradiation capsule and radiation field dose distribution detection device |
| CN105435363A (en) * | 2015-11-17 | 2016-03-30 | 吉林大学 | Method for making rapid prototyping oral cavity close quarter afterloading source applicator |
| CN105381534B (en) * | 2015-12-28 | 2018-12-07 | 上海昕健医疗技术有限公司 | Seeds implanted guide plate and its manufacturing method, device |
| CN105797284A (en) * | 2016-04-25 | 2016-07-27 | 张宏涛 | Radioactive particle radiation dose verification method and system |
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| CN110354403B (en) | 2021-09-17 |
| CN110354403A (en) | 2019-10-22 |
| CN106581873A (en) | 2017-04-26 |
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