• Journal of Radiation Protection and Research
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• 제33권1호
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• pp.35-40
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• 2008

석유화학 공정의 증류탑은 공정유체를 분리, 정제하는 중요한 장치 중의 하나로 가동효율은 설비의 생산성에 큰 영향을 미친다. 본 연구는 밀봉 감마선원을 이용하여 투과 감마선의 세기를 높이별로 측정함으로써 내부 밀도의 변화를 분석하여 공정의 가동 중 내부 상황에 대한 정보를 얻고자 하였다. 이를 위하여 한국원자력연구원에서 개발된 자동 증류탑 검사장치를 이용하여 증류탑 상부 양쪽에 밀봉 감마선원과 방사선검출기를 매달아 수직으로 내리면서 실험을 수행하였으며, 이때 감마선원으로는 Co-60 150 mCi과 방사선검출기로 BGO detector를 각각 사용하였다. 진단결과 설비 내부의 tray에는 구조적 결함이 관찰되지 않았으나, 유체분포를 고려할 때 상부는 기포층(vapor)의 밀도분포가 지배적인 반면에, 하단부에는 기포에 비해 유체가 상대적으로 많이 분포하는 것으로 계측되었다. 본 실험으로부터 밀봉 감마선원을 이용한 가동 중에 있는 대형 증류탑의 tray에 대한 구조적 건전성 및 내부 유체분포에 대한 정보를 성공적으로 제시하였다.

• Journal of Radiation Protection and Research
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• 제34권1호
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• pp.9-14
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• 2009

High density polyethylene (HDPE) is degraded due to a radiation-induced oxidation when it is used as a neutron moderator in a neutron counter for a nuclear material accounting of spent fuels. The HDPE exposed to the gamma-ray emitted from the fission products in a spent nuclear fuel results in a radiation-induced degradation which changes its original molecular structure to others. So a neutron moderating power variation of HDPE, irradiated by a gamma radiation, was investigated in this work. Five HDPE moderator structures were exposed to the gamma radiation emitted from a $^{60}Co$ source to a level of $10^5-10^9$ rad to compare their post-irradiation properties. As a result of the neutron measurement test with 5 irradiated HDPE structures and a neutron measuring system, it was confirmed that the neutron moderating power for the $10^5$ rad irradiated HDPE moderator revealed the largest decrease when the un-irradiated pure one was used as a reference. It implies that a neutron moderating power variation of HDPE is not directly proportional to the integrated gamma dose rate. To clarify the cause of these changes, some techniques such as a FTIR, an element analysis and a densitometry were employed. As a result of these analyses, it was confirmed that the molecular structure of the gamma irradiated HDPEs had partially changed to others, and the contents of hydrogen and oxygen had varied during the process of a radiation-induced degradation. The mechanism of these changes cannot be explained in detail at present, and thus need further study.

• Journal of Radiation Protection and Research
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• 제11권1호
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• pp.29-36
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• 1986

본 연구에서는 NaI검출기에서 감마스펙트럼 시뮤레이션 코드인 GESS를 개발하였다. 감마선에 의한 모든 상호작용이 시뮤레이션 과정에서 고려되었으며, 생성된 하전입자의 스펙트럼은 CSDA 모델에 기반을 두어 계산하였다. 매질내에서 입자 수송에 대한 해석수단으로는 몬테칼로 방법을 적용하였다. 코드의 검증을 위하여 1.33MeV의 입사 감마선에 대한 스펙트럼이 본 연구에서 개발된 코드에 의해 계산되었으며, 계산된 스펙트럼은 대체적으로 실험에서 얻은 스펙트럼과 거의 동일한 분포를 나타내고 있다.

• Journal of Radiation Protection and Research
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• 제3권1호
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• pp.29-32
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• 1978

감마선을 방출(放出)하는 방사성발기물(放射性發棄物)드럼 5292개($42{\times}42{\times}3$) 저장시설(貯藏施設)의 적정(適正) 콘크리트 차폐체(遮蔽體) 두께를 산출(算出)하였다. 발기물(發棄物)이 여러가지 종류(種類)의 방사성원소(放射性元素)로 구성(構成)되어 있다고 할때 평균(平均)한 감마선 에너지와 개개(個個) 감마선 에너지에 대하여 계산(計算)한 결과(結果)를 서로 비교(比較)하였다. 그 결과(結果) 적정차폐체(適正遮蔽體)의 두께는 50cm 정도(程度)로 판명(判明)되었다. 그런데 평균(平均) 감마선 에너지에 근거(根據)하여 계산(計算)한 선량치(線量値)는 개개(個個) 감마선 에너지에 대한 값보다 동일(同一)두께의 차폐체(遮蔽體)에 대해서 훨씬 적었다.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.215-224
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• 2001

In order to comply with revised national regulationson radiological protection and to implement recent nuclear data and dose conversion factors, KOPEC developed a new point kernel gamma and beta ray shielding analysis computer program. This new code, named VisualShield, adopted mass attenuation coefficient and buildup factors from recent ANSI/ANS standards and flux-to-dose conversion factors from the International Commission on Radiological Protection (ICRP) Publication 74 for estimation of effective/equivalent dose recommended in ICRP 60. VisualShieid utilizes graphical user interfaces and 3-D visualization of the geometric configuration for preparing input data sets and analyzing results, which leads users to error free processing with visual effects. Code validation and data analysis were performed by comparing the results of various calculations to the data outputs of previous programs such as MCNP 4B, ISOSHLD-II, QAD-CGGP, etc.

• Nuclear Engineering and Technology
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• 제51권3호
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• pp.853-859
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• 2019

A comprehensive study of photon interaction features has been made for some alloys containing Pd and Ag content to evaluate its possible use as alternative gamma radiations shielding material. The mass attenuation coefficient (${\mu}/{\rho}$) of the present alloys was measured at various photon energies between 81 keV-1333 keV utilizing HPGe detector. The measured ${\mu}/{\rho}$ values were compared to those of theoretical and computational (MCNPX code) results. The results exhibited that the ${\mu}/{\rho}$ values of the studied alloys are in the same line with results of WinXCOM software and MCNPX code results at all energies. Moreover, Pd75/Ag25 alloy sample has the maximum radiation protection efficiency (about 53% at 81 keV) and lowest half value layer, which shows that Pd75/Ag25 has superior gamma radiation shielding performance among the other compared alloys.

• 대한약학회:학술대회논문집
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• 대한약학회 2003년도 Proceedings of the Convention of the Pharmaceutical Society of Korea Vol.1
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• pp.159.1-159.1
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• 2003

This study deals with the radiation protection effect of the pretreatment of $\beta$-carotene and combination with selenium on the DNA damage in mice after whole body ${\gamma}$-irradiation. This was obtained the radioprotective effect by evaluation of DNA damage levels in mice spleen and blood after irradiation. Six-week-old ICR male mice were administrated with $\beta$-carotene and combination with selenium orally once a day for 5 days and then irradiated with 8.0 Gy of $\gamma$-ray at a dose rate of 1.0 Gy/min. (omitted)

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.1966-1973
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• 2023

Virtual reality technology has been widely used in the field of nuclear and radiation safety, dose rate computing in virtual environment is essential for optimizing radiation protection and planning the work in radioactive-controlled area. Because the CPU-based gamma dose rate computing takes up a large amount of time and computing power for voxelization of volumetric radioactive source, it is inefficient and limited in its applied scope. This study is to develop an efficient gamma dose rate computing code and apply into fast virtual simulation. To improve the computing efficiency of the point kernel algorithm in the reference (Li et al., 2020), we design a GPU-based computing framework for taking full advantage of computing power of virtual engine, propose a novel voxelization algorithm of volumetric radioactive source. According to the framework, we develop the GPPK(GPU-based point kernel gamma dose rate computing) code using GPU programming, to realize the fast dose rate computing in virtual world. The test results show that the GPPK code is play and plug for different scenarios of virtual simulation, has a better performance than CPU-based gamma dose rate computing code, especially on the voxelization of three-dimensional (3D) model. The accuracy of dose rates from the proposed method is in the acceptable range.

• Journal of Radiation Protection and Research
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• 제46권2호
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• pp.48-57
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• 2021

Background: In this study, the complexities of step-and-shoot intensity-modulated radiation therapy (IMRT) plans in magnetic resonance-guided radiation therapy systems were evaluated. Materials and Methods: Overall, 194 verification plans from the abdomen, prostate, and breast sites were collected using a ⁶⁰Co-based ViewRay radiotherapy system (ViewRay Inc., Cleveland, OH, USA). Various plan complexity metrics (PCMs) were calculated for each verification plan, including the modulation complexity score (MCS), plan-averaged beam area (PA), plan-averaged beam irregularity, plan-averaged edge (PE), plan-averaged beam modulation, number of segments, average area among all segments (AA/Seg), and total beam-on time (TBT). The plan deliverability was quantified in terms of gamma passing rates (GPRs) with a 1 mm/2% criterion, and the Pearson correlation coefficients between GPRs and various PCMs were analyzed. Results and Discussion: For the abdomen, prostate, and breast groups, the average GPRs with the 1 mm/2% criterion were 77.8 ± 6.0%, 79.8 ± 4.9%, and 84.7 ± 7.3%; PCMs were 0.263, 0.271, and 0.386; PAs were 15.001, 18.779, and 35.683; PEs were 1.575, 1.444, and 1.028; AA/Segs were 15.37, 19.89, and 36.64; and TBTs were 18.86, 19.33, and 5.91 minutes, respectively. The various PCMs, i.e., MCS, PA, PE, AA/Seg, and TBT, showed statistically significant Pearson correlation coefficients of 0.416, 0.627, -0.541, 0.635, and -0.397, respectively, with GPRs. Conclusion: The area-related metrics exhibited strong correlations with GPRs. Moreover, the AA/Seg metric can be used to estimate the IMRT plan accuracy without beam delivery in the ⁶⁰Co-based ViewRay radiotherapy system.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.3051-3057
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• 2021

The concrete is considered as an important radiation shielding material employed widely in nuclear reactors, particle accelerators, laboratory hot cells and other different radiation sources. The present research is dedicated to the shielding properties study of the ordinary concrete reinforced with different weight fractions of lead oxide micro/nano particles. Lead oxide particles were fabricated by chemical synthesis method and their properties including the average size, morphological structure, functional groups and thermal properties were characterized by XRD, FESEM-EDS, FTIR and TGA analysis. The gamma ray mass attenuation coefficient of concrete composites has been calculated and measured by means of the Monte Carlo simulation and experimental methods. The simulation process was based on the use of MCNP Monte Carlo code where the mass attenuation coefficient (μ/ρ) has been calculated as a function of different particle sizes and filler weight fractions. The simulation results showed that the employment of the lead oxide filler particles enhances the mass attenuation coefficient of the ordinary concrete, drastically. On the other hand, there are approximately no differences between micro and nano sized particles. The mass attenuation coefficient was increased by increasing the weight fraction of nanoparticles. However, a semi-saturation effect was observed at concentrations more than 10 wt%. The experimental process was based on the fabrication of concrete slabs filled by different weight fractions of nano lead oxide particles. The mass attenuation coefficients of these slabs were determined at different gamma ray energies using ²²Na, ¹³⁷Cs and ⁶⁰Co sources and NaI (Tl) scintillation detector. The experimental results showed that the HVL parameter of the ordinary concrete reinforced with 5 wt% of nano PbO particles was reduced by 64% at 511 keV and 48% at 1332 keV. Reasonable agreement was obtained between simulation and experimental results and showed that the employment of nano PbO particles is more efficient at low gamma energies up to 1Mev. The proposed concrete is less toxic and could be prepared in block form instead of toxic lead blocks.