• Title/Summary/Keyword: 광중성자

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Evaluation of Photoneutron Energy Distribution in the Radiotherapy Room (방사선치료실 내의 광중성자 에너지 분포 평가)

  • Park, Euntae;Ko, Seongjin;Kim, Junghoon;Kang, Sesik
    • Journal of radiological science and technology
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    • v.37 no.3
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    • pp.223-231
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    • 2014
  • Medical linear accelerator is widely used in radiation treatment field, and high energy photons, above 10 MV nominal accelerator voltage, are commonly utilized for the radiation treatment. However, these high energy photons lead the photo-nuclear reaction and the generation of photo-neutrons are accompanied. Thus, these problematic factors are issued in the view of radiation protection. Therefore, linear accelerator and radiation treatment room are simulated from MCNPX program in this study. The measurement points of interest are selected and analyzed, and the resulting effects derived from the properties of photo-neutron are evaluated. Therefore, we realized that the number of generating photo-neutrons was decreased by depending on the distance from the source. No matter what the nominal energy is set, the rates thermal neutrons to fast neutrons are marginal. It is founded that the amount of the thermal neutrons were decreased by depending on the distance from the source.

Evaluation of Photoneutron Dose in Radiotherapy Room Using MCNPX (MCNPX를 이용한 방사선 치료실의 광중성자 선량 평가)

  • Park, Eun-Tae
    • The Journal of the Korea Contents Association
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    • v.15 no.6
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    • pp.283-289
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    • 2015
  • Recently, high energy photon radiotherapy is a growing trend for increasing therapy results. Commonly, if you use high energy photons above 6~8 MeV nominal accelerator voltage, It lead the photo-nuclear reaction and the generation of photo-neutron are accompanied and these problematic factors are issued in the view of radiation protection. Therefore, in this study analyzed for dose distribution of photo-neutron in radiotherapy room based on MCNPX. As a result, absorbed dose is increased sharply from 10 MV to 12 MV. It was founded that the rapid increasement of photoneutron fluence was related to the absorbed dose at above 10 MV. Also, in case of the recommendation of ICRP 103, the outcome of an exchanged equivalent dose which based on calculated an absorbed dose, showed lower equivalent dose than ICRP 60 by reflecting the contribution of secondary photon for absorbed dose of human body in the low energy band.

Study on the Photoneutrons Produced in 15 MV Medical Linear Accelerators : Comparison of Three-Dimensional Conformal Radiotherapy and Intensity-Modulated Radiotherapy (15 MV 의료용 선형가속기에서 발생되는 광중성자의 선량 평가 - 3차원입체조형방사선치료와 세기조절방사선치료의 비교 -)

  • Yang, Oh-Nam;Lim, Cheong-Hwan
    • Journal of radiological science and technology
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    • v.35 no.4
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    • pp.335-343
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    • 2012
  • Intensity-modulated radiotherapy(IMRT) have the ability to provide better dose conformity and sparing of critical normal tissues than three-dimensional radiotherapy(3DCRT). Especially, with the benefit of health insurance in 2011, its use now increasingly in many modern radiotherapy departments. Also the use of linear accelerator with high-energy photon beams over 10 MV is increasing. As is well known, these linacs have the capacity to produce photonueutrons due to photonuclear reactions in materials with a large atomic number such as the target, flattening filters, collimators, and multi-leaf collimators(MLC). MLC-based IMRT treatments increase the monitor units and the probability of production of photoneutrons from photon-induced nuclear reactions. The purpose of this study is to quantitatively evaluate the dose of photoneutrons produced from 3DCRT and IMRT technique for Rando phantom in cervical cancer. We performed the treatment plans with 3DCRT and IMRT technique using Rando phantom for treatment of cervical cancer. An Rando phantom placed on the couch in the supine position was irradiated using 15 MV photon beams. Optically stimulated luminescence dosimeters(OSLD) were attached to 4 different locations (abdomen, chest, head and neck, eyes) and from center of field size and measured 5 times each of locations. Measured neutron dose from IMRT technique increased by 9.0, 8.6, 8.8, and 14 times than 3DCRT technique for abdomen, chest, head and neck, and eyes, respectively. When using IMRT with 15 MV photonbeams, the photoneutrons contributed a significant portion on out-of-field. It is difficult to prevent high energy photon beams to produce the phtoneutrons due to physical properties, if necessary, It is difficult to prevent high energy photon beams to produce the phtoneutrons due to physical properties, if necessary, it is need to provide the additional safe shielding on a linear accelerator and should therefore reduce the out-of-field dose.

Evaluation of Photoneutron Dose for Prostate Cancer Radiation Therapy by Using Optically Stimulated Luminescence Dosimeter (OSLD) (전립선암 방사선치료 시 광자극발광선량계를 이용한 광중성자선량 평가)

  • Lee, Joo-Ah;Back, Geum-Mun;Kim, Yeon-Soo;Son, Soon-Yong;Choi, Kwan-Woo;Yoo, Beong-Gyu;Jeong, Hoi-Woun;Jung, Jae-Hong;Kim, Ki-Won;Min, Jung-Whan
    • Journal of radiological science and technology
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    • v.37 no.2
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    • pp.125-134
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    • 2014
  • This study is to provide basic information regarding photoneutron doses in terms of radiation treatment techniques and the number of portals in intensity-modulated radiation therapy (IMRT) by measuring the photoneutron doses. Subjects of experiment were 10 patients who were diagnosed with prostate cancer and have received radiation treatment for 5 months from September 2013 to January 2014 in the department of radiation oncology in S hospital located in Seoul. Thus, radiation treatment plans were created for 3-Dimensional Conformal Radiotherapy (3D-CRT), Volumetric-Modulated Arc Radiotherapy (VMAT), IMRT 5, 7, and 9 portals. The average difference of photoneutron dose was compared through descriptive statistics and variance analysis, and analyzed influence factors through correlation analysis and regression analysis. In summarized results, 3D-CRT showed the lowest average photoneutron dose, while IMRT caused the highest dose with statistically significance (p <.01). The photoneutron dose by number of portals of IMRT was $4.37{\pm}1.08mSv$ in average and statistically showed very significant difference among the number of portals (p <.01). Number of portals and photoneutron dose are shown that the correlation coefficient is 0.570, highly statistically significant positive correlation (p <.01). As a result of the linear regression analysis of number of portals and photoneutron dose, it showed that photoneutron dose significantly increased by 0.373 times in average as the number of portals increased by 1 stage. In conclusion, this study can be expected to be used as a quantitative basic data to select an appropriate IMRT plans regarding photoneutron dose in radiation treatment for prostate cancer.

A Study on Radiation Exposure using Nominal Risk Coefficients (명목위험계수를 활용한 방사선 피폭에 관한 연구)

  • Joo-Ah Lee;Jong-Gil Kwak;Cheol-Min Jeon
    • Journal of the Korean Society of Radiology
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    • v.18 no.4
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    • pp.383-389
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    • 2024
  • In this study, we aimed to analyze the probability of secondary cancer occurring in the abdomen, a normal organ, due to photoneutron exposure during intensity-modulated radiotherapy for prostate cancer. The design of the radiation treatment plan for prostate cancer was established as a daily prescription dose of 220 cGy, a total of 35 treatments, and 7700 cGy. The experimental equipment was a True Beam STx (Varian, USA) linear accelerator from Varian. The energy used in the experiment was 15 MV, and the treatment plan was designed so that the photoneutron dose would be generated within the planning target volume (PTV). The radiation treatment plan was an Eclipse System (Varian Ver. 10.0, USA), and the number of irradiation portals was set to 5 to 9. The irradiation angle was designed so that 95% of the prescription dose area was set to 0 to 320°, and the number of beamlets per irradiation portal was set to 100. The optically stimulated luminescence dosimeter used in this study to measure the dose of photoneutrons was designed to measure photoneutron doses by coating 6LiCO3 on a device containing aluminum oxide components. It was studied that there is a minimum of 7.07 to 11 cases per 1,000 people with secondary cancer due to the photoneutron dose to the abdomen during intensity-modulated radiotherapy. In this study, we studied the risk of secondary radiation dose that may occur during intensity-modulated radiotherapy, and we expect that this will be used as meaningful data related to the probabilistic effects of radiation in the future.

A Study on the Thyroid dose high-energy Radiation Therapy of Lung Cancer (폐암 고에너지 방사선치료 시 갑상선 피폭에 관한 연구)

  • Yang, oh-nam;Lim, cheong-hwan
    • Proceedings of the Korea Contents Association Conference
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    • 2015.05a
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    • pp.167-168
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    • 2015
  • 고에너지 의료용 선형가속기를 이용한 폐암 방사선치료 시 갑상선에 미치는 선량을 평가하였다. 산란광자의 영향은 3DCRT 시 평균 27.9mSv, IMRT에 있어서는 43.6mSv로 평가 되었다. 광중성자의 영향은 3DCRT 시 평균 3.2mSv, IMRT에 있어서는 평균 4.7mSv로 평가 되었다. 산란광자와 광중성자 모두 3DCRT 보다 IMRT가 높은 것으로 평가 되었다. 본 연구를 통하여 고에너지를 이용한 방사선치료 시 인접한 정상조직에 상당한 양의 산란선량이 영향을 주는 것으로 평가된 바와 같이 방사선을 이용한 암 치료 종사자는 이러한 내용을 충분히 인지하여 피폭 저감화를 위한 노력이 필요할 것으로 사료된다.

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A Study on the Thyroid dose high-energy Radiation Therapy of Lung Cancer (폐암 고에너지 방사선치료 시 갑상선 피폭에 관한 연구)

  • Yang, Oh-Nam;Lim, Cheong-Hwan
    • Proceedings of the Korea Contents Association Conference
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    • 2014.11a
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    • pp.181-182
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    • 2014
  • 고에너지 의료용 선형가속기를 이용한 폐암 방사선치료 시 갑상선에 미치는 선량을 평가하였다. 산란광자의 영향은 3DCRT 시평균 27.9mSv, IMRT에 있어서는 43.6mSv로 평가 되었다. 광중성자의 영향은 3DCRT 시 평균 3.2mSv, IMRT에 있어서는 평균 4.7mSv로 평가 되었다. 산란광자와 광중성자 모두 3DCRT 보다 IMRT가 높은 것으로 평가 되었다. 본 연구를 통하여 고에너지를 이용한 방사선치료 시 인접한 정상조직에 상당한 양의 산란선량이 영향을 주는 것으로 평가된 바와 같이 방사선을 이용한 암치료 종사자는 이러한 내용을 충분히 인지하여 피폭 저감화를 위한 노력이 필요할 것으로 사료된다.

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하나로 1차 배관의 중성자 발생원 분석

  • 김명섭;홍광표;전병진
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.227-232
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    • 1998
  • 하나로 1차 배관에서 중성자를 측정하고 발생 원인을 분석하였으며, 이를 통하여 중성자 계측 계통을 이용하여 핵연료 파손을 감시할 수 있는 가능성을 검토하였다. 중성자 측정에는 BF$_3$비례 계수관을 이용하였고, 1차 배관의 주 방사선원인 N-16에 의한 감마선 펄스의 영향은 무시 할 정도로 작았다. 중성자의 발생 원인을 규명하기 위해 원자로 정지 전후에 중성자 계수율의 변화를 측정하였다. 편자로의 정상 운전시 1차 배관에서 발생되는 중성자는 물속의 중수소가 고에너지 감마선을 흡수하여 방출하는 광중성자와 핵연료의 표면 오염에 의해 발생된 지발 중성자라고 가정하여 원자로 정지 전후의 발생량 변화를 계산하였다. 계산 결과와 측정값을 비교하여 1차 배관 주변에서 측정된 중성자 가운데 지발 중성자가 약 70 %, N-16에 의한 광중성자가 약 30%임을 확인하였다. 핵연료의 표면 오염 정도로 발생하는 지발 중성자도 민감하게 측정되므로, 이러한 지발 중성자 계측법이 핵연료의 손상 여부를 알아낼 수 있는 유용한 방법임을 확인할 수 있었다.

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