• Title/Summary/Keyword: Proton accelerator

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Present Status of the Proton Therapy Project at the Wakasa Wan Energy Research Center

  • Kyo Kume;Shigekazu Fukuda;Sadayoshi.Fukumoto;Hisakazu Hamachi;Ha, Takashi.segawa;Satoshi Hatori;Yutaka Hayashi;Go Kagiya;Shuji Kakiuchi
    • Proceedings of the Korean Society of Medical Physics Conference
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    • 2002.09a
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    • pp.171-173
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    • 2002
  • Present status of the proton therapy project at the Wakasa Wan Energy Research Center, Japan, is reported. Construction of the accelerator system was finished in 2001, followed by some trials of the production of the flat clinical irradiation field for the clinical usage. After the patient positioning system with X-ray CT was verified, the first clinical trial was started for two patients with prostate cancer.

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A Thermal hydraulic Investigation on ADSR Liquid Lead Target

  • Kim, Ju Y.;Byung G. Huh;Chang H, Chung;Tae Y. song;Park, Won S.
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.666-671
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    • 1998
  • Computational fluid dynamics(CFD) code FLUENT[11 was used to simulate the thermal hydraulic processes occuring in conceptual design of the accelerator-driven subcritical reactor(ADSR) liquid lead target. The purpose of the analysis is to investigate the thermal hydraulic characteristics of liquid lead as ADSR target material with various target geometries and injection locations of proton beam. In the calculation analysis, the local temperature of the liquid lead target rises to the boiling temperature very rapidly When the proton beam is injected from the bottom of the target system, the duration time to reach the boiling temperature is longer and the temperature distribution is flatter than other cases.

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CURRENT RESEARCH ON ACCELERATOR-BASED BORON NEUTRON CAPTURE THERAPY IN KOREA

  • Kim, Jong-Kyung;Kim, Kyung-O
    • Nuclear Engineering and Technology
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    • v.41 no.4
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    • pp.531-544
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    • 2009
  • This paper is intended to provide key issues and current research outcomes on accelerator-based Boron Neutron Capture Therapy (BNCT). Accelerator-based neutron sources are efficient to provide epithermal neutron beams for BNCT; hence, much research, worldwide, has focused on the development of components crucial for its realization: neutron-producing targets and cooling equipment, beam-shaping assemblies, and treatment planning systems. Proton beams of 2.5 MeV incident on lithium target results in high yield of neutrons at relatively low energies. Cooling equipment based on submerged jet impingement and micro-channels provide for viable heat removal options. Insofar as beam-shaping assemblies are concerned, moderators containing fluorine or magnesium have the best performance in terms of neutron accumulation in the epithermal energy range during the slowing-down from the high energies. NCT_Plan and SERA systems, which are popular dose distribution analysis tools for BNCT, contain all the required features (i.e., image reconstruction, dose calculations, etc.). However, detailed studies of these systems remain to be done for accurate dose evaluation. Advanced research centered on accelerator-based BNCT is active in Korea as evidenced by the latest research at Hanyang University. There, a new target system and a beam-shaping assembly have been constructed. The performance of these components has been evaluated through comparisons of experimental measurements with simulations. In addition, a new patient-specific treatment planning system, BTPS, has been developed to calculate the deposited dose and radiation flux in human tissue. It is based on MCNPX, and it facilitates BNCT efficient planning based via a user-friendly Graphical User Interface (GUI).

The Formation of Nitride and Enhancement of Mechanical Properties of Al Alloy by Nitrogen Implantation (Al합금에서 질소이온주입에 의한 질화물 형성과 기계적 특성 향상)

  • Jeong, Jae-Pil;Lee, Jae-Sang;Kim, Kye-Ryung;Choi, Byung-Ho
    • Journal of the Korean institute of surface engineering
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    • v.39 no.5
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    • pp.235-239
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    • 2006
  • The aluminum nitride(AlN) layer on Al7075 substrate has been formed through nitrogen ion implantation process. The implantation process was performed under the conditions : 100 keV energy, total ion dose up to $2{\times}10^{18}\;ions/cm^2$. XRD analysis showed that aluminum nitride layers were formed by nitrogen implantation. The formation of Aluminum nitride enhanced surface hardness up to 265HK(0.02 N) from 150HK(0.02 N) for the unimplanted specimen. Micro-Knoop hardness test showed that wear resistance was improved about 2 times for nitrogen implanted specimens above $5\;{\times}\;10^{17}\;ions/cm^2$. The friction coefficient was measured by Ball-on-disc type wear tester and was decreased to 1/3 with increasing total nitrogen ion dose up to $1\;{\times}\;10^{18}ions/cm^2$. The enhancement of mechanical properties was observed to be closely associated with AlN formation. AES analysis showed that the maximum concentration of nitrogen increased as ion dose increased until $5\;{\times}\;10^{17}\;ions/cm^2$.

Design of muon production target system for the RAON μSR facility in Korea

  • Jeong, Jae Young;Kim, Jae Chang;Kim, Yonghyun;Pak, Kihong;Kim, Kyungmin;Park, Junesic;Son, Jaebum;Kim, Yong Kyun;Lee, Wonjun;Lee, Ju Hahn
    • Nuclear Engineering and Technology
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    • v.53 no.9
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    • pp.2909-2917
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    • 2021
  • Following the launch of Rare Isotope Science Project in December 2011, a heavy ion accelerator complex in South Korea, named RAON, has since been designed. It includes a muon facility for muon spin rotation, relaxation, and resonance. The facility will be provided with 600 MeV and 100 kW (one-fourth of the maximum power) proton beam. In this study, the graphite target in RAON was designed to have a rotating disk shape and was cooled by radiative heat transfer. This cool-down process has the following advantages: a low-temperature gradient in the target and the absence of a liquid coolant cooling system. Monte Carlo simulations and ANSYS calculations were performed to optimize the target system in a thermally stable condition when the 100 kW proton beam collided with the target. A comparison between the simulation and experimental data was also included in the design process to obtain reliable results. The final design of the target system will be completed within 2020, and its manufacturing is in progress. The manufactured target system will be installed at the RAON in the Sindong area near Daejeon-city in 2021 to carry out verification experiments.

Dose Distribution of 100 MeV Proton Beams in KOMAC by using Liquid Organic Scintillator (액체 섬광체를 이용한 100 MeV 양성자 빔의 선량 분포 평가)

  • Kim, Sunghwan
    • Journal of radiological science and technology
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    • v.40 no.4
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    • pp.621-626
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    • 2017
  • In this paper, an optical dosimetric system for radiation dose measurement is developed and characterized for 100 MeV proton beams in KOMAC(Korea Multi-Purpose Accelerator Complex). The system consists of 10 wt% Ultima GoldTM liquid organic scintillator in the ethanol, a camera lens(50 mm / f1.8), and a high sensitivity CMOS(complementary metal-oxide-semiconductor) camera (ASI120MM, ZWO Co.). The FOV(field of view) of the system is designed to be 150 mm at a distance of 2 m. This system showed sufficient linearity in the range of 1~40 Gy for the 100 MeV proton beams in KOMAC. We also successfully got the percentage depth dose and the isodose curves of the 100 MeV proton beams from the captured images. Because the solvent is not a human tissue equivalent material, we can not directly measure the absorbed dose of the human body. Through this study, we have established the optical dosimetric procedure and propose a new volume dose assessment method.

Fabrication and Optimization of a Fiber-optic Dosimeter for Proton Beam Therapy Dosimetry (의료용 양성자선 계측을 위한 광섬유 방사선량계의 제작 및 최적화)

  • Jang, Kyoung-Won;Cho, Dong-Hyun;Yoo, Wook-Jae;Seo, Jeong-Ki;Lee, Bong-Soo;Hwang, Eui-Jung;Shin, Dong-Ho;Park, Sung-Yong
    • Progress in Medical Physics
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    • v.21 no.1
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    • pp.29-34
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    • 2010
  • In this study, we have fabricated a fiber-optic dosimeter for a proton beam therapy dosimetry. We have measured scintillating lights with the various kinds of organic scintillators and selected the BCF-12 as a sensor-tip material due to its highest light output and peak/plateau ratio. To determine the optimum diameter of BCF-12, we have measured scintillating lights according to the energy losses of proton beams in a water phantom. Also, we determined the adequate length of organic scintillator by measuring scintillating lights according to the incident angles of proton beam. Using an optimized fiber-optic dosimeter, we have measured scintillating lights according to the dose rates and monitor units of proton accelerator.

Dosimetry by Using EBT2 Film for Total Skin Electron Beam Therapy (TSET) (전신 피부 전자선 치료(TSET)에서 EBT2 필름을 사용한 선량측정)

  • Hwang, Ui-Jung;Rah, Jeong-Eun;Jeong, Ho-Jin;Ahn, Sung-Hwan;Kim, Dong-Wook;Lee, Sang-Yeob;Lim, Young-Gyung;Yoon, Myong-Geun;Shin, Dong-Ho;Lee, Se-Byeong;Park, Sung-Young;Pyo, Hong-Ryull;Chung, Weon-Kuu
    • Progress in Medical Physics
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    • v.21 no.1
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    • pp.60-69
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    • 2010
  • For treatment of Total Skin Electron beam Therapy (TSET), measurement of dose at various conditions is need on the contrary to usual radiotherapy. When treating TSET with modified Stanford technique based on linear accelerator, the energy of treatment electron beam, the spatial dose distribution and the actual doses deposited on the surface of the patient were measured by using EBT2. The measured energy of the electron beam was agreed with the value that measured by ionization chamber, and the spatial dose distribution at the patient position and the doses at several point on the patient's skin could be easily measured by EBT2 film. The dose on the patient that was measured by EBT2 film showed good agreement with the data measured simultaneously by TLD. With the results of this study, it was proven that the EBT2 film can be one of the useful dosimeter for TSET.

400 MeV/nucleon 12C Ions Shielding Benchmark Calculations using MCNPX with Different Nuclear Data Libraries (400 MeV/nucleon 12C 이온의 MCNPX 와 핵자료를 이용한 차폐 벤치마킹 계산)

  • Shin, Yun Sung;Kim, yong min;Kim, dong hyun;Jung, nam suk;Lee, hee seock
    • Journal of the Korean Society of Radiology
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    • v.9 no.5
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    • pp.295-300
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    • 2015
  • There are various type of particle accelerators such as Kyoungju 100-MeV proton beam accelerator in Korea. And Korea plans to build large particle accelerator such as heavy ion accelerator and 4th generation light source facility. The accelerated high energy particles of these facility produce 2nd neutron after nuclear reaction with target materials. And then these 2nd neutron activate structural materials and surrounding environment. Accordingly, it is important to consider the activation and shielding calculation on design of facility for safety operation. In this study, we tried to calculate and compare the neutron flux from the interaction $^{la}150$ beam with target material(Cu) according to thickness of iron and concrete shielding material by MCNPX 2.7 with nuclear library JENDL/HE 07and la150. To verify the properties of nuclear library, we compared computational results with experimental value. These results can be used for dose evaluation technology in planning of the shielding of large particle accelerator.

A Study of Radiation Exposure in Proton Therapy Facility (양성자치료기 가속기 시설에서의 작업종사자의 방사선 피폭 연구)

  • Lee, Sang-Hoon;Shin, Dong-Ho;Yoon, Myong-Geun;Shin, Jung-Wook;Rah, Jeong-Eun;Kwak, Jung-Won;Park, Sung-Yong;Shin, Kyung-Hwan;Lee, Doo-Hyun;Ahn, Sung-Hwan;Kim, Dae-Yong;Cho, Kwan-Ho;Lee, Se-Byeong
    • Progress in Medical Physics
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    • v.20 no.1
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    • pp.37-42
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    • 2009
  • Proton therapy facility, which is recently installed at National Cancer Center in Korea, generally produces a large amount of radiation near cyclotron due to the secondary particles and radioisotopes caused by collision between proton and nearby materials during the acceleration. Although the level of radiation by radioisotope decreases in length of time, radiation exposure problem still exists since workers are easily exposed by a low level of radiation for a long time due to their job assignment for maintenance or repair of the proton facility. In this paper, the working environment near cyclotron, where the highest radiation exposure is expected, was studied by measuring the degree of radiation and its duration for an appropriate level of protective action guide. To do this, we measured the radiation change in the graphite based energy degrader, the efficiency of transmitted beam and relative activation degree of the transmission beam line. The results showed that while the level of radiation exposure around cyclotron and beam line during the operation is much higher than the other radiation therapy facilities, the radiation exposure rate per year is under the limit recommended by the law showing 1~3 mSv/year.

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