Abstract: A neutron capture therapy system is provided, including a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall forming a space for accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly. A support module is disposed in the concrete wall, the support module is capable of supporting the beam shaping assembly and is used to adjust the position of the beam shaping assembly, and the support module includes concrete and a reinforcing portion at least partially disposed in the concrete. The neutron capture therapy system designs a locally adjustable support for the beam shaping assembly, so that the beam shaping assembly can meet the precision requirement, improve the beam quality, and meet an assembly tolerance of the target.

Abstract: Provided is an arthroscopic system including an disposable arthroscope having a distal end and a proximal end, and including a light source, a lens set, an image sensor, a transmitter, and a control interface. The arthroscopic system eliminates the possibility of infecting the patient with contaminated devices by its cost-effectively disposable arthroscope. Also provided is a method for image rotating in an arthroscopic system.

Abstract: A neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly, the concrete wall and a reinforcing portion at least partially disposed in the concrete wall are provided to support the beam shaping assembly, and more than 90% of weight of a material of the reinforcing portion is composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti. In the neutron capture therapy system, the reinforcing portion disposed in the concrete wall has good anti-activation performance. Therefore, compared with a conventional reinforced concrete structure, the radiation is further attenuated.

Abstract: A light emitting diode (LED) lamp includes: a housing; an thermally-conductive circuit board mounted inside the housing; a plurality of light emitting diodes (LEDs) mounted on the thermally-conductive circuit board; a plurality of pins arranged in the housing and electrically connected to the thermally-conductive circuit board; and a driving circuit mounted on the thermally-conductive circuit board, the driving circuit including a first heat-generating electronic element and a second heat-generating electronic element located on opposite surfaces of the thermally-conductive circuit board.

Abstract: Abeam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam, a moderator adjoining to the target, a reflector surrounding the moderator. The neutrons are moderated to epithermal neutron energies by the moderator, and part of the moderator disposed on the back of the target can be replaced so as to adjust the epithermal neutron energies. The reflector leads the neutrons deviated from the main axis back.

Abstract: The present disclosure provides a neutron capture therapy system including a beam shaping assembly. The beam shaping assembly includes a beam inlet; a neutron generator arranged into the beam shaping assembly, the neutron generator has nuclear reaction with an incident proton beam from the beam inlet to produce neutrons; a moderator adjacent to the neutron generator, the neutrons are moderated by the moderator to epithermal neutron energies; a reflector surrounding the neutron generator and the moderator, the reflector leads the deflected neutrons back to enhance epithermal neutron beam intensity; a beam outlet; and at least a movable member moving away from or close to the neutron generator, the movable member moves between a first position where the neutron generator is replaceable, and a second position where the neutron generator is irreplaceable. The neutron capture therapy system has a simple structure, and the neutron generator is easy to be replaced.

Abstract: An oscillation device includes an oscillator and a logic circuit. The oscillator generates an output oscillation signal. The logic circuit controls the oscillator according to the output oscillation signal, such that the output oscillation signal includes two different oscillation periods. The oscillation device may be used as a temperature-to-frequency converter without any bandgap reference circuit.

Abstract: Disclosed is a method for evaluating an irradiation angle of a beam, including a step of sampling the irradiation angle of the beam, wherein the irradiation angle of the beam is defined as being the direction of the vector of the irradiation point of the beam to the pre-set point of the tumor; and a step of calculating the track of the beam passing through the organs, wherein it is determined whether the tumor is fully covered within the effective treatment depth, and if so, entering the steps of calculating the evaluation coefficient, recording the irradiation conditions and calculating the results, and returning to the step of sampling the irradiation angle of the beam; and if not, entering the step of giving the worst evaluation coefficient and returning to the step of sampling the irradiation angle of the beam.

Abstract: A shielding material for shielding radioactive ray and preparation method thereof. The shielding material consists of water, a cementing material, a fine aggregate material, a coarse aggregate material and an additive, wherein the fine aggregate material consists of a borosilicate glass powder and a barite sand, and the coarse aggregate material consists of a barite. A content of boron element in the borosilicate glass powder accounts for 0.5%-1% of the total weight of the shielding material. A content of barium sulfate in the barite sand and the barite accounts for 71%-75% of the total weight of the shielding material. Other contents include water, the cementing material and the additive, and a sum of contents of all components is 100% total weight of the shielding material.

Abstract: A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The material of the moderator is subjected to a powder sintering process using a powder sintering device so as to change powders or a power compact into blocks. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

Abstract: A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The material of the moderator is subjected to a powder sintering process using a powder sintering device so as to change powders or a power compact into blocks. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

Abstract: A neutron capture therapy system and a target for a particle beam generating device, which may improve the heat dissipation performance of the target, reduce blistering and extend the service life of the target. The neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron generating device includes an accelerator and a target, and a charged particle beam generated by acceleration of the accelerator interacts with the target to generate a neutron beam. The target includes an acting layer, a backing layer and a heat dissipating layer, the acting layer interacts with the charged particle beam to generate the neutron beam, the base layer supports the action layer, and the heat dissipating layer includes a tubular member composed of tubes arranged side by side.

Abstract: A beam shaping assembly (10) used in a neutron capture system and capable of changing an irradiation range of a neutron beam. The beam shaping assembly includes: a beam inlet (11), a target (12), a moderator (13) adjoining the target (12), a reflector (14) surrounding the moderator (13), a thermal neutron absorber (15) adjoining the moderator (13), a radiation shield (16) arranged inside the beam shaping assembly (10), and a beam outlet (17). The beam shaping assembly (10) further includes replacement components (21, 22) that can be attached to and detached from the beam shaping assembly (10) to change the irradiation range of the neutron beam.

Abstract: A neutron capture therapy system and a target for a particle beam generating device, which may improve the heat dissipation performance of the target, reduce blistering and extend the service life of the target. The neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron generating device includes an accelerator and a target, and a charged particle beam generated by acceleration of the accelerator interacts with the target to generate a neutron beam. The target includes an acting layer, a backing layer and a heat dissipating layer, the acting layer interacts with the charged particle beam to generate the neutron beam, the base layer supports the action layer, and the heat dissipating layer includes a tubular member composed of tubes arranged side by side.

Abstract: A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The material of the moderator is subjected to a powder sintering process using a powder sintering device so as to change powders or a power compact into blocks. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

Abstract: The present application provides an arthroscopic system, which comprises an disposable arthroscope having a distal end and a proximal end, and comprising a light source, a lens set, an image sensor, a transmitter, and a control interface. The present application eliminates the possibility of infecting the patient with contaminated devices by its cost-effectively disposable arthroscope. The present application also provides a method for image rotating in an arthroscopic system.

Abstract: Structures and formation methods of an image sensor structure are provided. The image sensor structure is provided. The image sensor structure includes a substrate, a photodiode component in the substrate, and a grid structure over the substrate. The grid structure includes a bottom dielectric element over the substrate, a reflective element over the bottom dielectric element, and an upper dielectric element over the reflective element. The reflective element has a sidewall which is anti-corrosive in a basic condition and an acidic condition. The image sensor structure also includes a color filter element over the substrate and surrounded by the grid structure. The color filter element is aligned with the photodiode component.

Abstract: A neutron moderation material for use in a BNCT beam shaping assembly. The neutron moderation material comprises three elements, i.e., Mg, Al, and F, wherein the mass fraction of the Mg element is 3.5%-37.1%, the mass fraction of the Al element is 5%-90.4%, and the mass fraction of the F element is 5.8%-67.2%; the sum of the weights of the Mg, Al, and F elements is 100% of the total weight of the neutron moderation material. The neutron moderation material may be doped with a small amount of 6Li-containing substances, and the addition of the 6Li-containing substances effectively decreases the content of ?-rays in epithermal neutron beams.

Abstract: Structures and formation methods of an image sensor structure are provided. The image sensor structure is provided. The image sensor structure includes a substrate, a photodiode component in the substrate, and a grid structure over the substrate. The grid structure includes a bottom dielectric element over the substrate, a reflective element over the bottom dielectric element, and an upper dielectric element over the reflective element. The reflective element has a sidewall which is anti-corrosive in a basic condition and an acidic condition. The image sensor structure also includes a color filter element over the substrate and surrounded by the grid structure. The color filter element is aligned with the photodiode component.

Abstract: Disclosed is a method for evaluating an irradiation angle of a beam, including a step of sampling the irradiation angle of the beam, wherein the irradiation angle of the beam is defined as being the direction of the vector of the irradiation point of the beam to the pre-set point of the tumor; and a step of calculating the track of the beam passing through the organs, wherein it is determined whether the tumor is fully covered within the effective treatment depth, and if so, entering the steps of calculating the evaluation coefficient, recording the irradiation conditions and calculating the results, and returning to the step of sampling the irradiation angle of the beam; and if not, entering the step of giving the worst evaluation coefficient and returning to the step of sampling the irradiation angle of the beam.