| Paper | Title | Page |
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MOCH3 |
The Progress with Debugging and Commissioning of BRIF | |
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| We had mainly carried on the debugging and commissioning of CYCIAE-100 for Beijing Radioactive Ion-beam Facility (BRIF) in 2016. The installation and commissioning of south extraction system in the remaining works, the south proton beam lines and part of experimental target stations had been completed, meanwhile, the installation of partial shields for the fort section also had been finished in the large experimental hall, and they had been put into physical experiment for the first time. The debugging work of CYCIAE-100 went well, the maximum internal target beam was 1073uA, and the maximum external target beam had reached 45uA. It ws the first time that the CYCIAE-100 had provided proton beam 500 hours in 2016 for the physics experiment of single event effect, measurement of proton effective dose, white light neutron, and proton radiography. | ||
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TUPH24 |
BNCT Neutron Source Design based on Small Cyclotron | |
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| The key to BNCT is the production of high flux and good angular distribution of thermal neutrons and super-thermal neutrons. The neutron source produced by small cyclotron in the environment of hospital installation is safe, flexible and operable. Design the flux of different neutron components according to the requirements for treatment. Super-thermal neutron flux is requires 10e+8 n cm-2 s-1. This paper design a set of neutron production and neutron shaping equipment according to the requirement of neutron flux and dose limit. The obtained super-thermal neutron flux is 7.47e+8 n cm-2 mA-1, which achieves the design target. | ||
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TUPH28 |
Medical Small Cyclotron Maze Design | |
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| Abstract: The 14MeV proton cyclotron, which is used to produce radioactive isotopes such as 18FDG, produces a large number of neutrons in the process. Appropriate shielding design is required. The accelerator's power is almost lost on the production target, therefore, special shielding design is required for the neutron source. In the hospital, a maze design is usually used to block the neutron source. The dose distribution of the accelerator is obtained through the Monte Carlo simulation, according to this, a labyrinth wall is designed to meet dose-limiting conditions. | ||
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