• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2016.10a
• /
• pp.467-468
• /
• 2016

• Journal of the Korean Society of Radiology
• /
• v.13 no.1
• /
• pp.73-80
• /
• 2019

Neutrons are generated by the nuclear reaction, which is absorbed into the concrete wall and causes the activation during cyclotron operation. The purpose of this study is to investigate the effect of neutron activation and radiative concrete on concrete type. This experiment used Monte Carlo simulation and RESRAD model. The results of the experiment showed that the higher the content of Fe in concrete, the greater the shielding rate. The effect of $^{56}Fe(n,\;2np)^{54}Mn$ reaction on workers is also increased. However, radioactive nuclides have low activity and have very low impact on workers. Radioactive concrete should be treated as general wastes with less than its self-disposal tolerance level, and it should be recycled to the surface such as road repair rather than landfill to minimize the effect of $^{14}C$.

• Journal of the Korean Society of Radiology
• /
• v.15 no.4
• /
• pp.415-427
• /
• 2021

Korea Institute of Radiological and Medical Sciences has provided various beam irradiation services to researchers using a 50 MeV cyclotron beam line. In particular, since the neutron beam service uses the nuclear reaction between protons and beryllium, the possibility of activation of the irradiated sample increases by using a high current. In this study, MCNP 6.2 and FISPACT-II 4.0 were used to evaluate the possible activation during the 35 MeV 20 ㎂ neutron beam service, which is preferred by the researchers. As a result of the calculation, if the iron, copper, and tungsten samples were irradiated for more than 1 hour, long-lived radioisotopes were produced and their radioactivity exceeded the standard level for self-disposal. Under the conditions of 2 hours of daily irradiation, no activation occurred in the building materials, and the internal exposure of workers due to air activation inside the irradiation room was very insignificant. And when this air was discharged to environment, the radioactivity including this air was also satisfied the emission standard.

• Journal of the Korean Society of Radiology
• /
• v.11 no.6
• /
• pp.429-435
• /
• 2017

In order to increase the therapeutic effect of radiation, there has been an increase in the use of conventional photon therapy. The intensive care unit should pay more attention to the radiation safety evaluation due to the higher energy and the larger facility compared to the existing Photon treatment. These radiation safety evaluations are mainly performed by using Monte Carlo simulation, and the first thing to be done is geometric modeling. The Heavy-ion treatment facility uses synchrotron as the accelerating device, which is difficult to precisely model geometrically and is mostly modeled briefly. This study investigated the effect of simplification and precise implementation of Dipole magnet among the components of synchrotron acceleration device on the radiation safety evaluation. The results show that the simplified geometric model is overestimated with the precisely implemented geometric model. Therefore, it is considered that the radiological safety evaluation results in more reliable results of the precise geometric modeling.

• Journal of radiological science and technology
• /
• v.43 no.5
• /
• pp.389-395
• /
• 2020

The evaluation of radioactivated components of heavy-ion accelerator facilities affects the safety of radiation management and the exposure dose for workers. and this is an important issue when predicting the disposal cost of waste during maintenance and dismantling of accelerator facilities. In this study, the FLUKA code was used to simulate the proton treatment device nozzle and classify the radio-nuclides and total radioactivity generated by each component over a short period of time. The source term was evaluated using NIST reference beam data, and the neutron flux generated for each component was calculated using the evaluated beam data. Radioactive isotopes caused by generated neutrons were compared and evaluated using nuclide information from the International Radiation Protection Association and the Korea Radioisotope association. Most of the nuclides produced form of beta rays and electron capture, and short-lived nuclides dominated. However, In the case of ⁵⁴Mn, which is a radioactive product of iron, the effect of gamma rays should be considered. In the case of tritium generated from a material with a low atomic number, it is considered that handling care should be taken due to its long half-life.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.10a
• /
• pp.275.1-275
• /
• 1999

• Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
• /
• 2008.04c
• /
• pp.18-21
• /
• 2008

기존의 대부분의 안테나는 한정된 공간에서 한정범위의 인식이 곤란한 단점이 있었다. 이러한 단점을 개선하고 소형화를 위하여, 간단한 형태의 다이폴안테나를 설계 하였다. Ansoft사의 Designer를 이용하여 안테나 시뮬레이션을 수행 하였으며, 산업체의 자동화 공정이나, 컨베이어상에서 제품에 부착된 전자태그의 인식효율과 소형화를 고려하여 설계하였다. 설계한 안테나는 RFID 안테나의 소형화와 한정된 공간에서 Tag 의 인식을 위해 테프론 기판을 이용한 다이폴 형태로 구현 제작하였다. 본 연구결과 설계 제작된 안테나는, 도우넛형태의 방사패턴을 가지며, 협소한 지역에 전파를 방사시켜서, 주변의 불필요한 태그의 인식을 최소로 하였고, 실제로 컨베이어 장치를 이용하여 개발 제품의 성능 테스트를 수행하였으며, 그 결과 제품의 우수성을 검증 하였다.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
• /
• 2001.10a
• /
• pp.230-233
• /
• 2001

본 논문에서는 기존의 QMSA에 비해 안테나 전체 길이를 소형화함은 물론 전기력선이 미치는 범위가 제한받지 않도록 그라운드 판을 접어올린 좌측 평행 평판과 방사 패치사이 용량을 장하한 QMSA를 설계ㆍ제작하여 실제의 휴대전화기에 부착해서 안테나의 이득노화요인에 대해서 서술하였다. 안테나 성능 지표로서 휴대전화기케이스의 크기를 그라운드판으로 한 안테나를 설계하여 상용화된 HFSS프로그램에 의해서 리턴로스와 방사패턴등, 각종 손실을 고려한 개략적인 시뮬레이션을 행한 결과를 나타냈다. 또한 인체 근체에서 사용되고 있을 때의 휴대 전화용 안테나의 특성은 다른 사용상황에 있어서 안테나 급전점과 인체머리부분과의 간격, 인체머리부분과 안테나의 각도 등을 고려해서 인체에 미치는 전계강도를 시뮬레이션했다.

• Journal of radiological science and technology
• /
• v.39 no.1
• /
• pp.89-97
• /
• 2016

As previous studies to proceed with the evaluation of the radioactive at linear accelerator's shielding concrete wall. And the shielding wall was evaluated the characteristics for the incoming neutron. As a result, the shielding wall is the average amount of incoming neutrons 10 MV 4.63E-7%, 15 MV 9.69E-6%, showed the occurrence of 20 MV 2.18E-5%. The proportion of thermal neutrons of which are found to be approximately 18-33%. The neutron generation rate can be seen as a slight numerical order. However, in consideration of the linear accelerator operating time we can not ignore the effects of neutrons. Accordingly radioactive problem of the radiation shield wall of the treatment room will be this should be considered.

• The Journal of Korean Institute of Electromagnetic Engineering and Science
• /
• v.19 no.2
• /
• pp.214-222
• /
• 2008

The equivalent circuit for the RLH-TL is proposed considering radiation effects due to the inclusion of a series capacitor and shunt inductor in a unit cell for the right/left-handed transmission line(RLH-TL). The design equations to realize a specific phase shift at a given frequency is also provided. The S-parameters for unit cells with N=1, 3, 5, and 10 are analyzed in various aspects based on the EM and circuit simulations especially for the purpose of controlling radiation along RLH-TL's. A modification formula for the radiation rate per unit cell is also proposed for good agreement between the EM and circuit simulation results.