• 방사선산업학회지
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• 제18권1호
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• pp.95-100
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• 2024

To establish a radioactive waste life cycle history management system, a series of processes including waste generation, classification, packaging, storage, transportation, and disposal were reflected in the information management system. A preliminary review process was introduced to reduce the amount of radioactive waste generated and manage it efficiently. Through this, the amount of radioactive waste generated must be checked from the beginning of the research, and the generated radioactive waste must be thoroughly managed from the stage of generation to final disposal. In particular, in the case of radioactive waste data generated during nuclear facility operation and each experiment, a radioactive waste information management system must be operated to receive information from the waste generator and integrate it with processing information at the management stage. The application process for small-package containers was reflected so that information such as the generation facility of radioactive waste, generation facility, project information, types of radioactive waste, major radionuclides, etc. In the radioactive waste management process, the preceding steps are to receive waste history from the waste generators. This includes an application for a specified container with a QR label, pre-inspection, and management request. Next, the succeeding steps consist of repackaging, treatment, characterization, and evaluating the suitability of disposal, for a process to transparently manage radioactive wastes.

• 한국전자파학회논문지
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• 제19권11호
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• pp.1185-1192
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• 2008

본 논문에서는 고전압 스위치와 팻 다이폴 안테나로 구성되는 광대역 LC 오실레이터를 설계 및 제작하고 방사 특성에 관해 분석하였다. 제안된 광대역 LC 오실레이터는 Marx generator를 고전압 펄스 전원 장치로 사용하며 지향성을 높이기 위해 $90^{\circ}$ 코너 리플렉터를 사용한다. 시뮬레이션 및 측정 파형을 분석한 결과, 팻 다이폴을 연결하지 않은 고전압 스위치는 수신 전력을 기준으로 약 9%(${\lambda}_1=0.7\;m$)의 3 dB 대역폭을 가지며, 고전압 스위치와 팻 다이폴 안테나로 구성되는 LC 오실레이터는 약 30%(${\lambda}_2=1\;m$)의 대역폭을 가진다. 결과적으로 팻 다이폴 안테나가 방사 전력뿐만 아니라 동작 주파수 및 대역폭에 영향을 미치는 것을 확인할 수 있었다. 본 논문의 연구 내용은 고전압 스위치와 팻 다이폴 안테나로 구성되는 광대역 LC 오실레이터 설계 시 동작 주파수와 방사 전력을 결정하는데 있어서 매우 유용할 것으로 판단된다.

• 대한핵의학회지
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• 제3권1호
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• pp.73-82
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• 1969

The newly developed diagnostic method with application of $^{113}Sn-^{113m}In$ cow system ($^{113}Sn:\;T\frac{1}{2}$ 118 days, $^{113m}In:\;T\frac{1}{2}$ 1.7 hrs, 390 Kev, Single ${\gamma}$) has the remarkable advantages such as increased diagnostic ability by single large dose administration of $^{113m}In$ with no subsequent radiation hazard and shortened examining time. We reformed the research of following scope with the use of developed $^{113}Sn-^{113m}In$ cow (25 mCi) generator: The sizes of particles produced under various conditions were investigated, and possibility for application to the scannings of various organs such as brain, liver, lung, bone marrow and blood pool etc. were studied. Results: $^{113m}InCl_3$ solution eluted from diluted HCl solution (pH 1.5) passed through $^{113}Sn-^{113m}In$ generator, and there can be produced various sized particles of colloidal indium. And there observed the state of distribution of $^{113m}In$ in each organ which showed many differences according to the particle sizes of colloidal indium. The results are stated as follows: 1. The adjustment of pH is the most important factor in making the desirable particle size of colloidal indium. The colloid for blood pool showed the highest level as 7.1%/gm blood, at pH 1.7, the colloid of pH 3.5 for liver scanning showed the highest level, 88.4%, in the liver, the colloid pH 6 showed the highest level, 3.1%, in the spleen, and the colloid of pH 11.0 showed the highest level, 85.3%/gm, in the lung. 2. The colloid for liver scanning made with NaCl-NaOH system showed the highest liver uptake at pH 7.2, and at either higher or lower pH than 7.2 showed decrease of liver uptake more or less. 3. The activity of $^{113m}In$ eluted through $^{113}Sn-^{113m}In$ generator indicated over 90% in the initial 4 ml, and particularly 88.1%-86.0% in the initial 2 ml. 4. The incubation time, tempertaure and mechanical irritation related to colloid formation and coating of colloid were not the definite condition of influence.

• 시스템엔지니어링학술지
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• 제12권1호
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• pp.89-103
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• 2016

Due to safety of the plant, it became very clear the importance of study occurrence reactor coolant system (RCS) issues specially the primary water stress corrosion cracking (PWSCC). The Systems Engineering (SE) approach is characterized by the application of a structured engineering methodology for the design of a complex system or component. Robotic devices have been used for internal inspection, maintenance and performing remote welding and inspection in high-radiation areas. In this paper, PWSCC overview and inlay and over lay welding methodology introduced, concept of robotic device that can be inserted into the piping via Steam Generator (SG) main way to access to primary piping of pressurized water reactor (PWR) is developed based on SE methodology. A 3D model of the inspection system was developed along with the APR1400 (Advanced Power Reactor)reactor coolant systems (RCS) and internals with virtual 3D simulation of the operation for visualization to prove the validity of the concept.

• 전기학회논문지
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• 제64권2호
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• pp.222-227
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• 2015

This paper presents the optimal energy generation systems for economical EVs(Electric Vehicles) charging stations located in an island area. The system includes grid electricity, diesel generator and renewable energy sources of wind turbines and PV(Photovoltaic) panels. The independent generation system is designed with data resources such as annual average wind speed, solar radiation and the grid electricity price by calculating system cost under different structures. This sensitive analysis on the varying data resources allows for the configuration of the most economical generation system for charging stations by comparing initial capital, operating cost, NPC(Net Present Cost) and COE(Cost of Energy). Depending on the increase of the grid cost, the NPC variation of the most economical system which includes renewable energy generations and grid electricity can be smaller than those of other generation systems.

• Journal of Mechanical Science and Technology
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• 제17권9호
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• pp.1380-1387
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• 2003

When a cold HPSI (High pressure Safety Injection) fluid associated with an overcooling transient, such as SGTR (Steam Generator Tube Rupture), MSLB (Main Steam Line Break) etc., enters the cold legs of a stagnated primary coolant loop, thermal stratification phenomena will arise due to incomplete mixing. If the stratified flow enters the downcomer of the reactor pressure vessel, severe thermal stresses are created in a radiation embrittled vessel wall by local overcooling. As general thermal-hydraulic system analysis codes cannot properly predict the thermal stratification phenomena, RG 1.154 requires that a detailed thermal-mixing analysis of PTS (pressurized Thermal Shock) evaluation be performed. Also. previous PTS studies have assumed that the thermal stratification phenomena generated in the stagnated loop side of a partially stagnated primary coolant loop are neutralized in the vessel downcomer by the strong flow from the unstagnated loop. On the basis of these reasons, this paper focuses on the development of a 3-dimensional thermal-mixing analysis model using PHOENICS code which can be applied to both partial and total loop stagnated cases. In addition, this paper verifies the fact that, for partial loop stagnated cases, the cold plume generated in the vessel downcomer due to the thermal stratification phenomena of the stagnated loop is almost neutralized by the strong flow of the unstagnated loop but is not fully eliminated.

• 대한방사선기술학회지:방사선기술과학
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• 제35권4호
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• pp.315-319
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• 2012

본 연구는 위치 민감형 광 증폭 다이오드로부터 나오는 신호를 증폭 및 파형 변화 후 신호의 크기를 검출하여 일정시간 동안 유지시키는 뒷단 회로 개발에 관한 연구이다. 신호발생기에서 발생한 소신호를 증폭 소자를 통한 안정적인 증폭 후 미분회로를 통하여 신호 파형을 검출하기 수월한 형태로 변형 하고, peak/hold 회로에서 피크의 최대점을 일정시간 유지하여 신호의 수집을 원활하게 하였다. 본 회로에 대한 독립적인 성능 평가를 위하여 상용 장비로부터의 검사신호를 입력으로 사용하였다.

• 방사성폐기물학회지
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• 제19권1호
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• pp.51-58
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• 2021

Chemical decontamination of primary systems in a nuclear power plant (NPP) prior to commencing the main decommissioning activities is required to reduce radiation exposure during its process. The entire process is repeated until the desired decontamination factor is obtained. To achieve improved decontamination factors over a shorter time with fewer cycles, the appropriate flow characteristics are required. In addition, to prepare an operating procedure that is adaptable to various conditions and situations, the transient analysis results would be required for operator action and system impact assessment. In this study, the flow characteristics in the steady-state and transient conditions for the chemical decontamination operations of the Kori-1 NPP were analyzed and compared via the MARS-KS code simulation. Loss of residual heat removal (RHR) and steam generator tube rupture (SGTR) simulations were conducted for the postulated abnormal events. Loss of RHR results showed the reactor coolant system (RCS) temperature increase, which can damage the reactor coolant pump (RCP)s by its cavitation. The SGTR results indicated a void formation in the RCS interior by the decrease in pressurizer (PZR) pressure, which can cause surface exposure and tripping of the RCPs unless proper actions are taken before the required pressure limit is achieved.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.238-247
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• 2023

The present work represents a technical guideline for decommissioning a disused teletherapy machine model Theratron-780 and contains category one ⁶⁰Co radioactive source. The first section predicts the dose rate from the source in case of normal and radiological emergency situations via FLUKA-MC simulation code. Moreover, the dose assessment for the occupational during the whole process is calculated and compared to the measured values. A suggested cordoned area for safety and security in a radiological emergency is simulated. The second section lists the whole process's technical procedures, including (preview, dismantle, securing, transport and storage) of the disused teletherapy machine. Results show that the maximum obtained accumulated dose for occupational were found to be 24.5 ± 4.9 μSv in the dismantle and securing process in addition to 3.5 ± 1.8 μSv during loading on the transport vehicle and unloading at the storage facility. It was found that the measured accumulated dose for workers is in good agreement with the estimated one by uncertainty not exceeding 5% in normal operating conditions.

• 방사선산업학회지
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• 제10권4호
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• pp.219-225
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• 2016

The apron is one of the essential protectors to reduce the exposure dose of radiological technologists. This study is to provide a guideline for purchasing the aprons with excellent performance and to help reducing the exposure dose by measuring the shielding ration and uniformity of aprons according to lead equivalent and form types. The shielding ratio of aprons were measured by using radiation generator and dosimeter. Exposure conditions were 81 kVp, 25 mAs, source to image receptor distance (SID) 100 cm and field of view (FOV) $17^{{\prime}{\prime}}{\times}17^{{\prime}{\prime}}$. Exposure areas for front type and around type aprons were divided into 9 areas and for 2 pieces type aprons were divided into 3 areas of top and 4 areas of skirt. The uniformity of aprons were measured by using fluoroscopy and Image J. The 4 regions of interest (ROI) were set into acquired images and measured uniformity by measuring the standard deviation of pixel intensity in ROIs. In continuous shielding ration measurement of aprons according to exposure area, there was not statistical significance (P>0.05). In ANOVA test of aprons, there was statistical significance (P<0.01). In the results of sheilding ratio, although the aprons had equal lead equivalent, there were difference in shielding ratio from 83.59% to 98.15%. In the results of uniformity, the front type aprons with equal lead equivalent indicated the similar uniformity. However, the around type and 2 pieces type apron with equal lead equivalent indicated the different uniformity each other, from 1.8 to 22.2. If the performance evaluation in this study were conducted regularly before and after purchase the aprons, the exposure does to patients and radiological technologists could be reduced.