• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4329-4334
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• 2023

In this research, a prompt gamma neutron activation analysis (PGNAA) system is designed and constructed based on the use of a low power research reactor. For this purpose, despite the fact that this reactor did not include beam tubes, a thermal neutron beam line is installed inside the reactor tank. The extraction of the beam line from inside the tank made it possible to provide the neutron flux from the order of 106 n.cm^-2.s^-1. Also, because the beam line is installed in a tangential position to the reactor core, its gamma level has been minimized. Also, a suitable radiation shield is considered for the detector to minimize the background radiation and prevent radiation damage to the detector. Calculations and measurements are done in order to characterize this system, as well as spectrometry of several samples. The results of evaluations and experiments show that this system is suitable for performing PGNAA.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.189-195
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• 2017

Gel dosimeters have unique advantages in comparison with other dosimeters. Until now, these gels have been used in different radiotherapy techniques as a reliable dosimetric tool. Because dose distribution measurement is an important factor for appropriate treatment planning in different radiotherapy techniques, in this study, we evaluated the ability of the N-isopropylacrylamide (NIPAM) polymer gel to record the dose distribution resulting from the mixed neutron-gamma field of boron neutron capture therapy (BNCT). In this regard, a head phantom containing NIPAM gel was irradiated using the Tehran Research Reactor BNCT beam line, and then by a magnetic resonance scanner. Eventually, the $R_2$ maps were obtained in different slices of the phantom by analyzing T2-weighted images. The results show that NIPAM gel has a suitable potential for recording three-dimensional dose distribution in mixed neutron-gamma field dosimetry.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1998-2004
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• 2019

The Multi-Physics (MP) instrument is one of 20 neutron spectrometers planned in the China Spallation Neutron Source (CSNS). This paper presents a shielding calculation for the MP instrument using Monte Carlo codes MCNPX and FLUKA. First, the neutrons that escape from the CSNS decoupled water moderator and are delivered to the beam line of the MP instrument are calculated to use as the source term of the shielding calculation. Then, to validate the calculation method based on multiple variance reduction techniques, a cross check between MCNPX and FLUKA codes is performed by comparing the calculation results of the dose rate distribution on a simplified beam line model. Finally, a complete geometry model of the MP instrument is set up, and the primary parameters for the shielding design are obtained according to the calculated dose rate map considering different worst-case scenarios.

• 대한전기학회논문지:전기물성ㆍ응용부문C
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• 제52권12호
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• pp.545-552
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• 2003

When a Si PIN diode is exposed to fast neutrons, it results in displacement damage to the Si lattice structure of the diode. Defects induced from structural dislocation become effective recombination centers for carriers which pass through the base of a PIN diode. Hence, increasing the resistivity of the diode decreases the current for the applied forward voltage. This paper involves the development of a neutron sensor based on the phenomena of the displacement effect damaged by neutron exposure. The neutron effect on the semiconductor was analyzed. Several PIN diode arrays with various thickness and cross-section area of the intrinsic layer(I layer) were fabricated. Under irradiation tests with a neutron beam, the manufactured diodes have a good linearity to neutron dose and show that the increase of thickness of I layer and the decrease of cross-section of PIN diodes improve the sensitivity. Newly developed PIN diodes with thicker I layer and various cross section, were retested and then showed the best neutron sensitivity at the condition that the I layer thickness was similar to a side length. On the basis of two test results, final discrete PIN diodes with a rectangular shape were manufactured and the characteristics as neutron detectors were analyzed through the neutron beam test using on-line electronic dosimetry system. Developed PIN diode shows a good linearity as dosimetry in the range of 0 to 1,000cGy(Tissue) and its neutron sensitivity is 13mV/cGy at constant current of 5mA, that is three times higher than that of commercially available neutron detectors. And the device shows little dependency on the orientation of the neutron beam and a considerable stability in annealing test for a long period.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.333-335
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• 2001

The 2 GeV electron linac, the injector of the Pohang Light Source, was used as a photo-neutron source for radiation shielding research. The operational beam parameters are the nominal electron intensity of $0.5\;{\sim}5\;nC/sec$, the repetition rate of 10 Hz, and the beam pulse length of 1.0 nsec. One electron beam line was modified in order to install the target systems for producing pulsed photo-neutrons. The neutron spectrum and intensity were investigated by the time-of-flight technique. The reliable maximum energy of the measured neutrons was about 500 MeV. The number of neutrons above 20 MeV produced by one 1 GeV electron in a thick Pb target was about $6.45{\times}10^{-4}/sr$ at 90 degrees to the beam axis. The status of the photo-neutron source and the application research are presented.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.141-147
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• 2016

Background: A project for building a neutron time-of-flight (nTOF) facility is progressing. We expect that the construction will start in early 2016. Before that, a detailed simulation based on the current architectural drawings was performed to optimize the performance of our facility. Materials and Methods: Currently, several parts had been modified or changed from the original design to reflect requirements such as the layout of the electron beam line, shape of the vacuum chamber producing a neutron beam, and the underground layout of the nTOF facility. Detailed analysis for these modifications has been done with MCNP simulation. Results and Discussion: An overview of our photo-neutron source and KAERI nTOF facility were introduced. The numerical simulations for heat deposition, source term, and radiation shielding of KAERI nTOF facility were performed and the results are discussed. Conclusion: We are expecting that the construction of the KAERI nTOF facility will start in early 2016, and these results will be used as basic data.

• 한국의학물리학회지:의학물리
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• 제27권3호
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• pp.162-168
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• 2016

Proton therapy is increasingly being actively used in the treatment of cancer. In contrast to photons, protons have the potential advantage of delivering higher doses to the cancerous tissue and lower doses to the surrounding normal tissue. However, a range shifter is needed to degrade the beam energy in order to apply the pencil beam scanning technique to tumors located close to the minimum range. The secondary neutrons are produced in the beam path including within the patient's body as a result of nuclear interactions. Therefore, unintended side effects may possibly occur. The research related to the secondary neutrons generated during proton therapy has been presented in a variety of studies worldwide, since 2007. In this study, we measured the magnitude of the secondary neutron dose depending on the location of the detector and the use of a range shifter at the beam nozzle of the proton scanning mode, which was recently installed. In addition, the production of secondary neutrons was measured and estimated as a function of the distance between the isocenter and detector. The neutron dose was measured using WENDI-II (Wide Energy Neutron Detection Instruments) and a Plastic Water phantom; a Zebra dosimeter and 4-cm-thick range shifter were also employed as a phantom. In conclusion, we need to consider the secondary neutron dose at proton scanning facilities to employ the range shifter reasonably and effectively.

• Radiation Oncology Journal
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• 제24권4호
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• pp.280-284
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• 2006

목 적: 원자력의학원에 설치되어 있는 MC50 사이클로트론에서 생성되는 중성자선의 의학적 이용을 위하여 생물학적 특성을 평가하고자 하였다. 대상 및 방법: 35 MeV 양성자를 15 mm 베릴륨 표적에 부딪혀서 생성된 중성자선에 대하여 물리적 방사선선량을 측정한 후 체외실험(in-vitro)을 하였다. EMT-6 세포주(cell line)를 이용하여 $0{\sim}5\;Gy$의 중성자선을 조사 후 생존분획(surviving fraction)을 구하였다. 또한 감마선의 효과를 피하기 위하여 납차폐를 한 후에 동일 조건에서 생존분획을 구하였다. 엑스선 실험에서는 0, 2, 5, 10, 15 Gy를 조사 후 생존분획을 측정하였다. 결 과: MC50의 중성자선은 조사야 $26{\times}26\;cm^2$, 전류 $10{\mu}A$, 깊이 2 cm에서 84%의 중성자와 16%의 감마선으로 구성되어 있었고, 총선량률은 9.25 cGy/min이었다. 엑스선을 이용하여 측정한 생존분획곡선은 선형이차함수모델 (linear quadratic model)을 적용하였을 때 ${\alpha}/{\beta}$비는 0.611 (${\alpha}=0.0204,\;{\beta}=0.0334,\;R^2=0.999$)이었다. 중성자선에 있어서 생존분획곡선은 저선량 영역에서 어깨영역(shoulder area)을 가지고 있었고, 모든 실험에서 선형이차함수모델에 잘 맞았다. ${\alpha}$의 평균값은 -0.315 (범위, $-0.254{\sim}-0.360$)였고, ${\beta}$값은 0.247 (범위, $0.220{\sim}0.262$)이었다. 납차폐를 하였을 때에도 생존분획곡선에서 어깨영역은 없어지지 않았다. 중성자선의 RBE (relative biological effectiveness) 값은 생존분획이 0.1일 때 $2.07{\sim}2.19$ 범위였고, 0.01일 때 $2.21{\sim}2.35$였다. 결 론: MC50에서 생성된 중성자선은 상당량의 감마선을 내포하고 있으며 이것이 생존분획곡선에서 어깨영역이 나타나는 데에 기여하였을 것이다. MC50의 중성자선의 RBE 값은 약 2.2였다.

• Radiation Oncology Journal
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• 제6권1호
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• pp.85-91
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• 1988

한국에너지연구소 원자력병원 싸이클로트론에 의해 생산되는 중성자를 임상에 적용시키기 위해, 이의 물리적 특성을 알기 위하여 방사선선량 측정실험을 시행하였다. 여기서 얻은 결과를 외국의 다른 치료기관에서 얻은 데이타와 비교 분석하였다. 중심축 선상의 심부선량백분율, build-up곡선, open과 쐐기등선량 곡선의 값이 4MV와 6MV X-ray값의 중간에 위치하였다. 최대선량의 build-up은 피부아래 1.35cm에 위치했으며 입사 선량은 약 $40\%$였다. 출력인자는 $6\times6cm$의 조사야에서 0.894, $30\times30cm$의 조사야에서는 1.187이었다. 중성자선의 X-ray오염도는 $10\times10cm$ 조사야에서 심부 2cm에서 $4.9\%$였다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2013년도 제44회 동계 정기학술대회 초록집
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• pp.537-537
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• 2013

Cyclotron-accelerated ion beams are used for various researches, such as nuclear physics, nuclear chemistry, biotechnology, and material sciences including radio-isotope production. Recently considerable applications are asked to the cyclotron development undertaken to meet user requirements of various ions'energies, intensities, and their pulsed beams. For instance, a cocktail beam acceleration technique rapidly changing the ion species and energies was developed to irradiating integrated circuit chips. Also a chopping system in a cyclotron injection line is considered for producing a pulsed ion beam with a relatively long period compared with that generated by the resonance frequency. For the research in neutron time-of-flight measurement, a single-pulsed beam with a repetition interval of the order of mili-seconds or longer is necessary to have a good resolution and to remove background events. In this paper a feasibility of pulsed beam with an external ion source is simulated by adopting a combination system of a chopper accompanying with a bunching stage in the injection line and an additional chopper after the exit of the cyclotron in order to produce beam pulses with a range of $1{\mu}s{\sim}1ms$ periods from a resonance RF cycle. The pulseperiod will be adjusted by chopping the number of beam bunches from the injected pulses in the injection line. However, the longer pulses will have reduced number of beam pulses and sacrificed beam currents. Because the beam users need an intense single pulsed beam, a careful tuning of the acceleration phase and a high-intense external ion source are necessary to achieve an intense single-pulsed beam from the cyclotron. It is essential to strictly match the acceleration phase of injected beams in the central region of the cyclotron to improve its efficiency. An effect of space charge at each pulse from the ion source will be also considered.