• Nuclear Engineering and Technology
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• v.49 no.2
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• pp.411-425
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• 2017

Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose-risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

• Journal of Radiation Protection and Research
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• v.12 no.1
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• pp.40-47
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• 1987

The amount of the radionuclide release to the environment during a LOCA and its radiological consequence are assessed, for a 900MWe French PWR which is similar to the KNU 9/10, according to RFS V.1.a, in which the source term has been revised more conservatively after the TMI accident. The assessed result shows that the whole body and thyroid doses at the site boundary(500m) for 2 hours after the release are 66 mrem and 13.5 rem, respectively, and are within the corresponding limits. It is expected, however, that the thyroid dose would exceed the limit if the fraction of the organic iodine is over 10% of the iodine inventory.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.1
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• pp.95-106
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• 2019

The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experiences by U.S. operators have mainly focused on deterministic risk assessment, which is standardized by the U.S. Nuclear Regulatory commission (NRC) and focuses only on the consequences of risk. However, the International Atomic Energy Agency (IAEA) has suggested an alternative to the deterministic approach, called the risk matrix technique. The risk matrix technique considers both the consequence and likelihood of risk. In this study, decommissioning stages, processes, and activities are organized under a work breakdown structure. Potential accidents in the decommissioning process of NPPs are analyzed using the composite risk matrix to assess both radiological and non-radiological hazards. The levels of risk for all potential accidents considered by U.S. NPP operators who have performed decommissioning were estimated based on their consequences and likelihood of events.

• Journal of the Korean Arthroscopy Society
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• v.15 no.2
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• pp.158-164
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• 2011

As the instruments as well as techniques for hip arthroscopy have developed, the interests and understandings of acetabular labral tear have also increased. As a consequence, the diagnosis itself was increased. However, it is still difficult to be diagnosed accurately in an ordinary clinic. In this brief review, the clinical and radiological characteristics and diagnostic implications of acetabular labral lesions were described to help the surgeon to make a right decision.

• Journal of radiological science and technology
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• v.5 no.1
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• pp.21-34
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• 1982

When unattenuated x-ray radiation passes through the object it is transmitted and scattered from objectes and impinging on the film. During this process certain radiation is absorbed within the object and others transmitted in reduced scattering. The scattering radiation influence upon radiation image quality, confining x-ray beam which means scattering radiation produce increased fog on x-ray film image and as a consequence decrease contrast and less detail of the film there for the elimination of fog and for absorbing scattered radiation, the grid has been used between the object and the film in order to rid of scattering rays. Using grid is good method for the qualification of the better image as well as in using air gap technique. The grid is easy to manipulate and promote good efficiency which is defined by ICRU and JIS. It is the purpose to study for eliminating scattered radiation from the tissue equivalent acryl phantom using grid, we have studied and evaluated the grid permeability about the x-ray exposure, the selection of grid ratio according to phantom thickness, on x-ray exposure are performed as follows. 1. The penetrating ratio of primary x-ray is remarkably decreased by increasing of the grid ratio, but it is almost not influenced in KVP difference and phantom thickness. 2. The scattered radiation is proportionaly increased by thickness of the phantom, having nothing to do with grid ratios. 3. The relative between the penetration rate of primary and secondary x-ray is improved by increasing grid ratio, and decreased by phantom thickness, and slightly decreased by high tube voltage. 4. The grid of 5:1 and 10:1 ratio are adequate to the phantom of 10cm and 15cm thickness, respectively.

• Maxillofacial Plastic and Reconstructive Surgery
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• v.18 no.1
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• pp.78-86
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• 1996

This is a retrospective study of 31 patients, who were diagnosed as bilateral TMJ internal derangement in consequence of magnetic resonance imaging (MRI) of the temporomandibular joint (TMJ) at Department of Dentistry, Ajou University Hospital, and who were compared clinical findings with radiological findings. The results obtained were as follows. 1. The average of the patients of bilateral TMJ internal derangement was 27.3 years with a range from 12 to 74 years, and 93.6% of the patients were yonger than 40 years of age. The male-female ratio was 1 : 6.8, and the females of $20{\sim}29$ years were most common in 35.5%. 2. In the patients of bilateral TMJ internal derangement, the patients who complained clinical symptoms bilaterally were 38.7% and the patients who complained clinical symptoms untilaterally were 61.3%. 3. The most common disc position of bilateral TMJ internal derangement was anterior disc displacement without reduction on both sides in 38.7%. The most common disc configuration of bilateral TMJ internal derangement was biconcave on both sides and amorphous on both sides in closed mouth, and was amorphous on both sides in open mouth. 4. In the patients of bilateral TMJ internal derangement, the joints which really showed clinical symptoms were most common in anterior displacement without reduction of 48.9%.

• Nuclear Engineering and Technology
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• v.16 no.3
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• pp.136-140
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• 1984

A new medal is presented in order to evaluate the risk from a nuclear facility following accidents directly combining the on-site meteorological data using the Monte Carlo Method. To estimate the radiological detriment to the surrounding population-at-large (collective dose equivalent), in this study the probability distribution of each meteorological element based upon on-site data is analyzed to generate atmospheric dispersion conditions. The random sampling is used to select the dispersion conditions at any given time of effluent releases. In this study it is considered that the meteorological conditions such as wind direction, speed and stability are mutually independent and each condition satisfies the Markov condition. As a sample study, the risk of KNU-1 following the large LOCA was calculated, The calculated collective dose equivalent in the 50 mile region population from the large LOCA with 50 percent confidence level is 2.0$\times$10$^2$ man-sievert.

• Journal of radiological science and technology
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• v.31 no.3
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• pp.293-298
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• 2008

This study is aimed to investigate the change of serum compositions of mice caused by the irradiation. The 3Gy radiation with 10MeV Linac was once irradiated to whole body of mice and their serum was collected to conduct 14 biochemical analyses. With the collected data, t-test was performed. As the result, the significant change was confirmed in the following 3 compositions. First, the glucose level of the normal control group was $185.43{\pm}14.93$, but the irradiation group was found to be $220.00{\pm}17.58$, which shows significant difference(p<0.001). Second, the BUN(blood urea nitrogen) measurement showed lower value($15.70{\pm}1.48$) in the irradiation group than the normal control group($19.61{\pm}1.65$), which indicates the significant difference in mean value (p<0.01). Third, the measurement of albumin resulted in lower value of $2.89{\pm}0.25$ in irradiation group than $3.19{\pm}0.34$ of the normal control group, which shows the significant difference in mean value(p<0.05). In consequence, the serum of the mice irradiated with 3Gy radiation caused significant change in 3 compositions; glucose, Blood urea nitrogen(BUN) and albumin.

• Journal of radiological science and technology
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• v.36 no.4
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• pp.313-318
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• 2013

Positron emission tomography/computed tomography (PET/CT) imaging with fluorodeoxyglucose (FDG) have been used as a powerful fusion modality in nuclear medicine not only for detecting cancer but also for staging and therapy monitoring. Nevertheless, there are various causes of FDG uptake in normal and/or benign tissues. The purpose of present study was to investigate whether additional delayed imaging can improve the diagnosis to differentiate the rates of FDG uptake at axillary lymph nodes (ALN) between malignant and benign in breast cancer patients. 180 PET/CT images were obtained for 27 patients with ALN uptake. The patients who had radiotherapy and chemotherapy were excluded from the study. $^{18}F$-FDG PET/CT scan at 50 min (early phase) and 90 min (delayed phase) after $^{18}F$-FDG injection were included in this retrospective study. The staging of cancers was confirmed by final clinical according to radiologic follow-up and pathologic findings. The standardized uptake value (SUV) of ALN was measured at the Syngo Acquisition Workplace by Siemens. The 27 patients included 18 malignant and 9 ALN benign groups and the 18 malignant groups were classified into the 3 groups according to number of metastatic ALN in each patient. ALNs were categorized less than or equal 3 as N1, between 4 to 9 as N2 and more than 10 as N3 group. Results are expressed as the mean${\pm}$standard deviation (S.D.) and statistically analyzed by SPSS. As a result, Retention index (RI-SUV max) in metastasis was significantly higher than that in non-metastasis about 5 fold increased. On the other hand, RI-SUV max in N group tended to decrease gradually from N1 to N3. However, we could not prove significance statistically in malignant group with ANOVA. As a consequence, RI-SUV max was good indicator for differentiating ALN positive group from node negative group in breast cancer patients. These results show that dual-time-point scan appears to be useful in distinguishing malignant from benign.

• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.89-95
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• 2014

In potential accident consequence assessments for the licensing approval of LWRs, the ground deposition of radionuclides released into the environment is not allowed into the models, as recommended in the U. S. Nuclear Regulatory Commission's regulatory guide. Meanwhile, it is allowed into the assessment models for the licensing approval of PHWRs with consideration of more detailed physical processes of radionuclides in the atmosphere. Under these backgrounds, importance of exposure dose by ground deposition was quantitatively evaluated and comprehensively discussed. For potential accidental releases of $^{137}Cs$ and $^{131}I$, total exposure doses were more conservative in case of without consideration of ground deposition than in case of with its consideration. It was because of that the depletion of air concentration resulting from ground deposition is more influential in the contribution to total exposure doses than additional doses from contaminated ground. The exposure doses by the inhalation of contaminated air showed the contribution of more than 90% in total exposure doses, depending on atmospheric stability, release period of radionuclides and distance from a release point. The exposure doses from contaminated ground showed less than 10% at most in contribution of total exposure doses. The ratios of total exposure doses in case of with consideration of deposition to without its consideration for $^{131}I$ were distinct than those for $^{137}Cs$. As the atmosphere is more stable, release duration of radionuclides is longer, distance from a release point is longer, it was more distinct.