• 제목/요약/키워드: Radiological Engineering

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A multilevel in space and energy solver for multigroup diffusion eigenvalue problems

  • Yee, Ben C.;Kochunas, Brendan;Larsen, Edward W.
    • Nuclear Engineering and Technology
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    • 제49권6호
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    • pp.1125-1134
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    • 2017
  • In this paper, we present a new multilevel in space and energy diffusion (MSED) method for solving multigroup diffusion eigenvalue problems. The MSED method can be described as a PI scheme with three additional features: (1) a grey (one-group) diffusion equation used to efficiently converge the fission source and eigenvalue, (2) a space-dependent Wielandt shift technique used to reduce the number of PIs required, and (3) a multigrid-in-space linear solver for the linear solves required by each PI step. In MSED, the convergence of the solution of the multigroup diffusion eigenvalue problem is accelerated by performing work on lower-order equations with only one group and/or coarser spatial grids. Results from several Fourier analyses and a one-dimensional test code are provided to verify the efficiency of the MSED method and to justify the incorporation of the grey diffusion equation and the multigrid linear solver. These results highlight the potential efficiency of the MSED method as a solver for multidimensional multigroup diffusion eigenvalue problems, and they serve as a proof of principle for future work. Our ultimate goal is to implement the MSED method as an efficient solver for the two-dimensional/three-dimensional coarse mesh finite difference diffusion system in the Michigan parallel characteristics transport code. The work in this paper represents a necessary step towards that goal.

Analysis and radiation dose assessment of 222Rn in indoor air at schools: Case study at Ulju County, Korea

  • Lee, ChoongWie;Choi, Sungyeol;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.806-813
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    • 2018
  • $^{222}Rn$ exists in nature in the form of a rare radioactive gas. In terms of environmental radiation, issues regarding $^{222}Rn$ have persisted because of its radiological hazardousness. Ulju County is one of the regions of Ulsan metropolitan city, with a population of 227,699. Ulju County has the highest density of industrial complexes in Korea. In this study, $^{222}Rn$ radioactivity concentration was measured and analyzed in 57 schools in Ulju County using 114 passive LR-115 type detectors to secure radiological safety and confirm basic information for reduction of resident exposure to $^{222}Rn$. The effective dose of $^{222}Rn$ was assessed to find the actual risk of the concentration surveyed in schools to human beings. The dose depended on four factors: subjects, $^{222}Rn$ concentration, dose coefficient, and time. The individuals subjected to dose estimation were classified into three types: students, teachers, and office workers. The subjects had different dwelling locations and times. The findings demonstrate that the radiological hazard to students and workers at schools in Ulju County owing to $^{222}Rn$ is negligible in terms of $^{222}Rn$ activity recommendation level.

Evaluation of dose received by workers while repairing a failed spent resin mixture treatment device

  • Choi, Woo Nyun;Byun, Jaehoon;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.442-448
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    • 2022
  • Intermediate-level radioactive waste (ILW) is not subject to legal approval for cave disposal in Korea. To solve this problem, a spent resin treatment device that separates 14C-containing resin from zeolite/activated carbon and desorbs 14C through a microwave device has been developed. In this study, we evaluated the radiological safety of the operators performing repair work in the event of a failure in such a device treating 1 ton of spent resin mixture per day. Based on the safety evaluation results, it is possible to formulate a design plan that can ensure the safety of workers while developing a commercialized device. When each component of the resin treatment device can be repaired from the outside, the maximum and minimum allowable repair times are calculated as 263.2 h and 27.7 h for the 14C-detached resin storage tank and zeolite/activated carbon storage tank, respectively. For at least 6 h per quarter, the worker's annual dose limit remains within 50 mSv/year; further, over 5 years, it remained within 100 mSv. At least 6 h of repair time per quarter is considered, under conservative conditions, to verify the radiological safety of the worker during repair work within that time.

Evaluation of radiological safety according to accident scenarios for commercialization of spent resin mixture treatment device

  • Choi, Woo Nyun;Byun, Jaehoon;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • 제54권7호
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    • pp.2606-2613
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    • 2022
  • Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a treatment capacity of 1 ton/day was evaluated. The results confirm that the device is radiologically safe in the event of an accident. This device desorbs 14C from the spent resin, allowing disposal as low-level waste instead of intermediate-level waste. The device also reduces overall waste by recycling the extracted 14C. Potential accident scenarios were explored to enable dose assessments for both internal and external exposure while preventing further spillage of the device and processing the spilled resin. The scenarios involved the development of a surface fracture on the resin mixture separator and microwave systems, which were operated under pressure and temperature of 0-6 bar and 0-150 ℃, respectively. In the case of accidents with separator and microwave device, the maximum allowable working time of worker were derived, respectively, considering external and internal exposures. When wearing the respirator corresponding to APF 50, in the case of the microwave device accident scenario, the radiological safety was confirmed when the maximum worker worked within 132.1 h.

Improvement of the Biocompatibility of Chitosan Dermal Scaffold by Rigorous Dry Heat Treatment

  • Kim, Chun-Ho;Park, Hyun-Sook;Gin, Yong-Jae;Son, Young-Sook;Lim, Sae-Hwan;Park, Young-Ju;Park, Ki-Sook;Park, Chan-Woong
    • Macromolecular Research
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    • 제12권4호
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    • pp.367-373
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    • 2004
  • We have developed a rigorous heat treatment method to improve the biocompatibility of chitosan as a tissue-engineered scaffold. The chitosan scaffold was prepared by the controlled freezing and lyophilizing method using dilute acetic acid and then it was heat-treated at 110$^{\circ}C$ in vacuo for 1-3 days. To explore changes in the physicochemical properties of the heat-treated scaffold, we analyzed the degree of deacetylation by colloid titration with poly(vinyl potassium sulfate) and the structural changes were analyzed by scanning electron microscopy, Fourier transform infrared (FT-IR) spectroscopy, wide-angle X-ray diffractometry (WAXD), and lysozyme susceptibility. The degree of deacetylation of chitosan scaffolds decreased significantly from 85 to 30% as the heat treatment time increased. FT-IR spectroscopic and WAXD data indicated the formation of amide bonds between the amino groups of chitosan and acetic acids carbonyl group, and of interchain hydrogen bonding between the carbonyl groups in the C-6 residues of chitosan and the N-acetyl groups. Our rigorous heat treatment method causes the scaffold to become more susceptible to lysozyme treatment. We performed further examinations of the changes in the biocompatibility of the chitosan scaffold after rigorous heat treatment by measuring the initial cell binding capacity and cell growth rate. Human dermal fibroblasts (HDFs) adhere and spread more effectively to the heat-treated chitosan than to the untreated sample. When the cell growth of the HDFs on the film or the scaffold was analyzed by an MTT assay, we found that rigorous heat treatment stimulated cell growth by 1.5∼1.95-fold relative to that of the untreated chitosan. We conclude that the rigorous dry heat treatment process increases the biocompatibility of the chitosan scaffold by decreasing the degree of deacetylation and by increasing cell attachment and growth.

The Qualitative Analysis of Single Shot Fast Spin Echo (SSFSE) and Maximum Intensity Projection (MIP) on Magnetic Resonance Cholangiopancreatography

  • Park, Cheol-Soo;Cho, Jae-Hwan;Lee, Hae-Kag;Dong, Kyung-Rae;Chung, Woon-Kwan;Seok, Jong-Min;Han, Man-Seok;Lee, Sun-Yeob;Goo, Eun-Hoe;Kim, Eng-Chan
    • Journal of Magnetics
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    • 제17권2호
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    • pp.138-144
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    • 2012
  • 3-dimensional magnetic resonance cholangiopancreatography (MRCP) images reconstructed using the maximum intensity projection technique were analyzed qualitatively in patients diagnosed with pancreatobiliary diseases to determine their diagnostic utility. Single shot fast spin echo (SSFSE), fast spin echo (FSE) and 3-dimensional reconstructive images were acquired from 20 patients diagnosed histologically with pancreatobiliary diseases using a 3.0T MR scanner. According to qualitative analysis, the fast spin echo images and 3-dimensional reconstructed images of the hepatic duct, gall bladder and common bile duct had a higher signal to noise ratio (SNR) than the single shot fast spin echo images. Fast spin echo images and 3-dimensional reconstructed images did not show any differences. The contrast to noise ratio of the hepatic duct, gallbladder and common bile duct on the fast spin echo images and 3-dimensional reconstructed images was higher than that of the single shot fast spin echo images. The fast spin echo images and 3-dimensional reconstructed images showed similar quality.

Gamma-PF 보드를 이용한 아날로그 감마카메라의 디지털화 연구 (A Study of Digitalizing Analog Gamma Camera Using Gamma-PF Board)

  • 김희중;소수길;봉정균;김한명;김장휘;주관식;이종두
    • 대한의용생체공학회:의공학회지
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    • 제19권4호
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    • pp.351-360
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    • 1998
  • 아날로그 감마카메라에 비해 디지털 카메라는 Q.C가 편리하고, Calibration과 조작이 매우 쉬운 장점들을 갖고 있어 영상 질을 향상시킬 뿐만 아니라 진단의 정확도를 높일 수 있다. 더욱이, 디지털 카메라로 획득한 디지털 영상은 PACS(Picture Archiving and Communication System) 뿐만 아니라 원격진료에도 활용될 수 있다. 그러나, 많은 병원들이 아직도 아날로그 카메라를 사용하고 있고 이들을 디지털 카메라로 대체하기는 어려운 상황에 있다. 본 연구는 아날로그 감마카메라를 디지털화 할 수 있는지의 가능성을 보는 것이었다. 카메라를 디지털화 한 후 균일도 계수능력 등의 물리적 특성을 측정하였다. 임상에서의 사용 가능성을 보기 위해 아날로그 시스템과 디지털 시스템을 동시에 연결하여 임상 데이터들을 획득하였다. 이들의 결과는 임상환경에서 아날로그 카메라를 디지털화 하 수 있다는 가능성을 보여주었다.

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Virtual calibration of whole-body counters to consider the size dependency of counting efficiency using Monte Carlo simulations

  • Park, MinSeok;Kim, Han Sung;Yoo, Jaeryong;Kim, Chan Hyeong;Jang, Won Il;Park, Sunhoo
    • Nuclear Engineering and Technology
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    • 제53권12호
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    • pp.4122-4129
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    • 2021
  • The counting efficiencies obtained using anthropomorphic physical phantoms are generally used in whole-body counting measurements to determine the level of internal contamination in the body. Geometrical discrepancies between phantoms and measured individuals affect the counting efficiency, and thus, considering individual physical characteristics is crucial to improve the accuracy of activity estimates. In the present study, the counting efficiencies of whole-body counting measurements were calculated considering individual physical characteristics by employing Monte Carlo simulation for calibration. The NaI(Tl)-based stand-up and HPGe-based bed type commercial whole-body counters were used for calculating the counting efficiencies. The counting efficiencies were obtained from 19 computational phantoms representing various shapes and sizes of the measured individuals. The discrepancies in the counting efficiencies obtained using the computational and physical phantoms range from 2% to 33%, and the results indicate that the counting efficiency depends on the size of the measured individual. Taking into account the body size, the equations for estimating the counting efficiencies were derived from the relationship between the counting efficiencies and the body-build index of the subject. These equations can aid in minimizing the size dependency of the counting efficiency and provide more accurate measurements of internal contamination in whole-body counting measurements.

Measurements of Neutron Activation and Dose Rate Induced by High-Energy Medical Linear Accelerator

  • Kwon, Na Hye;Jang, Young Jae;Kim, Jinsung;Kim, Kum Bae;Yoo, Jaeryong;Ahn, So Hyun;Kim, Dong Wook;Choi, Sang Hyoun
    • 한국의학물리학회지:의학물리
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    • 제32권4호
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    • pp.145-152
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    • 2021
  • Purpose: During the treatments of cancer patients with a linear accelerator (LINAC) using photon beams with energies ≥8 MV, the components inside the LINAC head get activated through the interaction of photonuclear reaction (γ, n) and neutron capture (n, γ). We used spectroscopy and measured the dose rate for the LINAC in operation after the treatment ended. Methods: We performed spectroscopy and dose rate measurements for three units of LINACs with a portable high-purity Germanium (HPGe) detector and a survey meter. The spectra were obtained after the beams were turned off. Spectroscopy was conducted for 3,600 seconds, and the dose rate was measured three times. We identified the radionuclides for each LINAC. Results: According to gamma spectroscopy results, most of the nuclides were short-lived radionuclides with half-lives of 100 days, except for 60Co, 65Zn, and 181W nuclides. The dose rate for three LINACs obtained immediately in front of the crosshair was in the range of 0.113 to 0.129 µSv/h. The maximum and minimum dose rates measured on weekends were 0.097 µSv/h and 0.092 µSv/h, respectively. Compared with the differences in weekday data, there was no significant difference between the data measured on Saturday and Sunday. Conclusions: Most of the detected radionuclides had half-lives <100 days, and the dose rate decreased rapidly. For equipment that primarily used energies ≤10 MV, when the equipment was transferred after at least 10 minutes after shutting it down, it is expected that there will be little effect on the workers' exposure.

Review of Shielding Evaluation Methodology for Facilities Using kV Energy Radiation Generating Devices Based on the NCRP-49 Report

  • Na Hye Kwon;Hye Sung Park;Taehwan Kim;Sang Rok Kim;Kum Bae Kim;Jin Sung Kim;Sang Hyoun Choi;Dong Wook Kim
    • 한국의학물리학회지:의학물리
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    • 제33권4호
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    • pp.53-62
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    • 2022
  • In this study, we have investigated the shielding evaluation methodology for facilities using kV energy generators. We have collected and analysis of safety evaluation criteria and methodology for overseas facilities using radiation generators. And we investigated the current status of shielding evaluation of domestic industrial radiation generators. According to the statistical data from the Radiation Safety Information System, as of 2022, a total of 7,679 organizations are using radiation generating devices. Among them, 6,299 facilities use these devices for industrial purposes, which accounts for a considerable portion of radiation. The organizations that use these devices evaluate whether the exposure dose for workers and frequent visitors is suitable as per the limit regulated by the Nuclear Safety Act. Moreover, during this process, the safety shields are evaluated at the facilities that use the radiation generating devices. However, the facilities that use radiating devices having energy less than or equal to 6 MV for industrial purposes are still mostly evaluated and analyzed according to the National Council on Radiation Protection and Measurements 49 (NCRP 49) report published in 1976. We have investigated the technical standards of safety management, including the maximum permissible dose and parameters assessment criteria for facilities using radiation generating devices, based on the NCRP 49 and the American National Standards Institute/Health Physics Society N.43.3 reports, which are the representative reports related to radiation shielding management cases overseas.