• Title/Summary/Keyword: 원자력연구개발

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Modeling and analysis of dynamic heat transfer in the cable penetration fire stop system by using a new hybrid algorithm (새로운 혼합알고리즘을 이용한 CPFS 내에서의 일어나는 동적 열전달의 수식화 및 해석)

  • Yoon En Sup;Yun Jongpil;Kwon Seong-Pil
    • Journal of the Korean Institute of Gas
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    • v.7 no.4 s.21
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    • pp.44-52
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    • 2003
  • In this work dynamic heat transfer in a CPFS (cable penetration fire stop) system built in the firewall of nuclear power plants is three-dimensionally investigated to develop a test-simulator that can be used to verify effectiveness of the sealant. Dynamic heat transfer in the fire stop system is formulated in a parabolic PDE (partial differential equation) subjected to a set of initial and boundary conditions. First, the PDE model is divided into two parts; one corresponding to heat transfer in the axial direction and the other corresponding to heat transfer on the vertical planes. The first PDE is converted to a series of ODEs (ordinary differential equations) at finite discrete axial points for applying the numerical method of SOR (successive over-relaxation) to the problem. The ODEs are solved by using an ODE solver In such manner, the axial heat flux can be calculated at least at the finite discrete points. After that, all the planes are separated into finite elements, where the time and spatial functions are assumed to be of orthogonal collocation state at each element. The initial condition of each finite element can be obtained from the above solution. The heat fluxes on the vertical planes are calculated by the Galerkin FEM (finite element method). The CPFS system was modeled, simulated, and analyzed here. The simulation results were illustrated in three-dimensional graphics. Through simulation, it was shown clearly that the temperature distribution was influenced very much by the number, position, and temperature of the cable stream, and that dynamic heat transfer through the cable stream was one of the most dominant factors, and that the feature of heat conduction could be understood as an unsteady-state process.

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Development plan and Inspection Status of Hydrological Measuring Instrument (수문조사기기 검정현황 및 발전방안)

  • Kim, Ji Hun;Jang, Bok Jin;Kim, Ji Chan;Jung, SungWon
    • Proceedings of the Korea Water Resources Association Conference
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    • 2016.05a
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    • pp.213-213
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    • 2016
  • 수문조사기기의 검정은 수문조사에 활용할 기기를 일관되고 표준화된 기준으로 검사하여 수문조사에 적합한 기기인지 확인하는 것이다. 이러한 검정은 국가수문자료의 신뢰도를 높이고 유지하는 기본적이고 중요한 업무이다. 검정대상기기는 강수량측정기기, 유속측정기기, 수위측정기기, 부유사측정기기, 토양수분측정기기, 증발산량측정기기로 총 6가지이며, 2009년부터 국토교통부 위탁사업으로 한국건설기술연구원(유량조사사업단)에서 수행하고 있다. 특히 유량조사사업단에서는 유속측정기기를 제외한 나머지 5개 수문조사기기에 대해 검정을 수행하고 있다. 연도별로 2009년부터 2015년까지 98대, 334대, 572대, 539대, 359대, 682대, 690대로 총 3,274대를 검정하였고, 관측기종별로 강수량 1,579대, 수위 1,589대 부유사 23대, 토양수분 33대, 증발산량 50대이다. 신청기관별로는 국토교통부(홍수통제소) 1,847대, 환경부(국립환경과학원) 4대, 한국건설기술연구원(유량조사사업단 포함) 81대, K-water 338대, 한국수력원자력(주) 91대, 일반업체 913대에 대한 검정을 실시하였다. 검정을 실시한 강수량측정기기 1,579대 중 보정없이 합격된 기기는 1,495대, 허용오차기준에 미달되어 보정 실시 후 합격한 기기는 76대이며, 불합격 처리된 기기는 8대이다. 수위측정기기는 합격이 1,586대, 기준에 미달되어 불합격된 기기가 2대로 나타났다. 강수량측정기기의 각 연도대비 통계분석 결과 보정률은 2009년 97대 중 8대(8.2%), 2010년 194대 중 3대(1.5%), 2011년 180대 중 24대(13.3%), 2012년 175대 중 17대(9.7%), 2013년 165대 중 15대(9.1%), 2014년 547대 중 8대(1.5%), 2015년 221대 중 9대(4.1%)로 다소 낮은 수치로 나타났다. 이처럼 보정률이 낮게 나타난 이유는 관할기관의 검정을 위한 유지관리 및 사업자의 사전검사 등을 통해 감소한 것으로 판단되며, 이와 같은 결과는 수문자료의 품질 및 신뢰도 향상으로 이어졌다. 그러나 여전히 선진국에 비해 수문조사기기 검정의 중요성에 대한 인프라 구축이 미흡한 실정이다. 수문조사기기 검정의 선진국이라 할 수 있는 미국의 경우 USGS에서 HIF(Hydrogical Istrumentation Facility)라는 별도 조직을 운영하여 관측기기의 렌탈, 수리, 교정 및 검정, 개발, 교육 등 이러한 작업을 일괄 수행하고 있고 조직 내 자체 시설로 수중펌프 시험소, 자연과 유사한 환경에서 테스트 하는 장소, 대형온도챔버 등을 갖추고 있으며, 이러한 시설을 이용하여 기기의 교정 및 검정, 연구 등을 현장과 비슷한 환경에서 다양한 실험을 통해 검정방법을 비교, 분석하는 것을 볼 수 있다. 현재 우리나라의 수문조사기기는 다양한 방법으로 현장에 설치되어 검정방법의 다양성이 요구된다. 향후 우리나라도 HIF와 같이 다양하고 선진화된 시설과 기술을 개선하고 다각적인 시험 과정을 통해 수준 높은 검정방법체계를 갖추려는 노력이 필요하다.

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Factors Influencing The Perception of Continuing Medical Education for Radiological Technologist (방사선사 보수교육 인식에 영향을 미치는 요인)

  • Yang, Sung-Hee;Lee, Dong-Yeon
    • The Journal of the Korea Contents Association
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    • v.21 no.7
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    • pp.629-636
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    • 2021
  • The study analyzes the relationship between demand, satisfaction, and perception for non-face-to-face continuing medical education(CME) conducted in 2020 for 225 radiological technologist license holders working in the Busan area, and the factors that influence the positive perception of CME. T-test and one way ANOVA were used, and stepwise multiple regression analysis was performed. As a result, there were high demands for mobile publicity, professional radiological technologist, educational expenses support from institution heads, and CME. Male radiological technologist, over 50 years of age, and the more experienced they had a job chance, the more they had a positive perception. In the correlation between variables, the perception of the education system and the need for education showed a positive correlation. The higher the satisfaction with the education system, the higher the perception of the need for education. About 53% of the content was satisfied. Therefore, in order to raise awareness of CME, it is considered that policy changes to the education system are necessary first of all. It is considered that the search for the development of education content and educational content is necessary above all.

The Historical Understanding of the U. S. Secret Records Management (미국의 비밀기록관리체제에 대한 역사적 이해)

  • Lee, Kyong-Rae
    • The Korean Journal of Archival Studies
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    • no.23
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    • pp.257-297
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    • 2010
  • The U. S. government has a long history to classify and manage governmental records which are created, collected, and preserved for itself. During the colonial period before the independence, the U. S. mostly practiced the maintenances of secret records and restrictions of access to the records following a long convention without any specific legal authority. Since establishment of the U. S. Constitution, the government had kept secret records on the basis of constitutional authority. However, the U. S. government began to take shape the secret records management system when it participated in the World War I, which required the system to reflect the needs in reality to manage drastic increases in important military and foreign relation documents. The World War II made the U. S. government strengthen its secret records management system, and its conception of secret records management system at that time has sustained until now. It can be said that the current secret records management system of the U. S. government continues to be managed by constitutional authorities and the executive orders which are opt to change. This article intends to review the secret records management system of the U. S. from the initial history of the U. S. to the Cold War. To understand its system of secret management, the paper investigates the U. S. secret records management history by dividing into three periods: the period of establishment of its tradition(the Colonial era~just before the WWI); the period of taking shape of its system (the WWI~the WWII); and the period of current conception of its system. The criteria of these divisions are created based on the differences of the laws relevant to the secret records and the application methods of secret management system in reality.

Development of Dust Recycling System and Dust Cleaner in Pipe during Vitrification of Simulated Non-Radioactive Waste (모의 비방사성폐기물의 유리화시 발생 분진의 재순환처리장치 및 배관 내 침적분진에 의한 막힘 방지용 제진장치의 개발)

  • Choi Jong-Seo;You Young-Hwan;Park Seung-Chul;Choi Seok-Mo;Hwang Tae-Won;Shin Sang-Woon
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.06a
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    • pp.110-120
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    • 2005
  • For utilizing vitrification to treat low and intermediate level waste, industrial pilot plant was designed and constructed in October 1999 at Daejon, Korea through the joint research program among NETEC, MOBIS and SGN. More than 70 tests were performed on simulated IER, DAW etc. including key nuclide surrogate(Cs, Co); this plant has been shown to vitrify the target waste effectively and safely, however, some dust are generated from the HTF(High Temperature Filter) as a secondary waste. In case of long term operation, it is also concerned that pipe plugging can be occurred due to deposited dust in cooling pipe namely, connecting pipe between CCM(Cold Crucible Melter) and HTF. In this regard, we have developed the special complementary system of the off-gas treatment system to recycle the dust from HTF to CCM and to remove the interior dust of cooling pipe. Main concept of the dust recycling is to feed the dust to the CCM as a slurry state; this system is regarded as of an important position in the viewpoint of volume reduction, waste disposal cost and glass melt control in CCM. The role of DRS(Dust Recycling System) is to recycle the major glass components and key nuclides; this system is served to lower glass viscosity and increase waste solubility by recycling B, Na, Li components into glass melt and also to re-entrain and incorporate into glass melt like Cs, Co. Therefore dust recycling is helpful to control the molten glass; it is unnecessary to consider a separate dust treatment system like a cementation equipment. The effects of Dust Cleaner are to prevent the pipe plugging due to dust and to treat the deposited dust by raking the dust into CCM. During the pilot vitrification test, overall performance assessment was successfully performed; DRS and Dust Cleaner are found to be useful and effective for recycling the dust from HTF and also removing the dust in cooling pipe. The obtained operational data and operational experiences will be used as a basis of the commercial facility.

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Research on the Actual Condition of the radiation Safety Management(RSM) for the Educated Training of the Dental Diagnostics X-ray Generators (교육용 치과 엑스선 발생장치에 대한 방사선 안전 관리 실태 조사)

  • Lee, Mihyeon;Yu, Yunsik;Lee, Jaeseung;Im, Inchul
    • Journal of the Korean Society of Radiology
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    • v.8 no.7
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    • pp.467-477
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    • 2014
  • The purpose of this study is to offer data base for establishment of dental training x-ray generator based safety usage through surveying real radiation safety management state of radiation worker's in plan of operations that have dental training x-ray generators and use it. For it, comprehensive references were surveyed referring reports of current state of regulation technique development and domestic radiation safety evaluation and nuclear related legislation regarding radiation safety management of dental training x-ray generators. On the basis of it, questionnaires were filled in about respondent's general characteristic radiation safety manager's status current state of radiation safety management and the level of knowledge & consciousness. For the study, the survey was conducted to 224 people of radiation safety managers and university graduates training assistants and full-time professors who can treat dental training x-ray generators in education center. through this survey 95 questionnaires were used as analysis materials except the insufficient and omitted responses. As a method of analysis, the frequency and percentage were figured out with the general characteristics and safety manager's status. Chi-square test for frequency and correlation per question analysis and Pearson correlation analysis for crosslevel correlation were done with current state of radiation safety management and knowledge & consciousness level. As a result, running dental training x-ray generators was dealt with by 20's to 40's who have high education level over post undergraduate degree and major in dental hygienic. In addition, female have higher consciousness level for radiation safety management than male. It shows significal linear relation statistically(${\chi}^2$ >5, 0.1${\chi}^2$ >5, 0.3${\chi}^2$ >5, 0.3

A Study on the Dose Assessment Methodology Using the Probabilistic Characteristics of TL Element Response (확률분포 특성을 이용한 열형광선량계의 선량평가방법에 관한 연구)

  • Cho, Dae-Hyung;Oh, Jang-Jin;Han, Seung-Jae;Na, Seong-Ho;Hwang, Won-Guk;Lee, Won-Keun
    • Journal of Radiation Protection and Research
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    • v.23 no.3
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    • pp.123-138
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    • 1998
  • Characteristics of element responses of Panasonic UD802 personnel dosimeters in the X, ${\beta}$, ${\gamma}$, ${\gamma}/X$, ${\gamma}/{\beta}$ and ${\gamma}$/neutron mixed fields were assessed. A dose-response algorithm has been developed to decide the high probability of a radiation type and energy by using the distribution in all six ratios of the multi-element TLD. To calculate the 4-element response factors and ratios between the elements of the Panasonic TLDs in the X, $\beta$, and $\gamma$ radiation fields, Panasonic’s UD802 TLDs were irradiated with KINS’s reference irradiation facility. In the photon radiation field, this study confirms that element-3 (E3) and element-4 (E4) of the Panasonic TLDs show energy dependent both in low- and intermediate-energy range, while element-1 (E1) and element-2 (E2) show little energy dependency in the entire whole range. The algorithm, which was developed in this study, was applied to the Panasonic personnel dosimetry system with UD716AGL reader and UD802 TLDs. Performance tests of the algorithm developed was conducted according to the standards and criteria recommended in the ANSI N13.11. The sum of biases and standard deviations was less than 0.232. The values of biases and standard deviations are distributed within a triangle of a lateral value of 0.3 in the ordinate and abscissa, With the above algorithm, Panasonic TLDs satisfactorily perform optimum dose assessment even under an abnormal response of the TLD elements to the energy imparted. This algorithm can be applied to a more rigorous dose assessment by distinguishing an unexpected dose from the planned dose for the most practical purposes, and is useful in conducting an effective personnel dose control program.

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Very short-term rainfall prediction based on radar image learning using deep neural network (심층신경망을 이용한 레이더 영상 학습 기반 초단시간 강우예측)

  • Yoon, Seongsim;Park, Heeseong;Shin, Hongjoon
    • Journal of Korea Water Resources Association
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    • v.53 no.12
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    • pp.1159-1172
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    • 2020
  • This study applied deep convolution neural network based on U-Net and SegNet using long period weather radar data to very short-term rainfall prediction. And the results were compared and evaluated with the translation model. For training and validation of deep neural network, Mt. Gwanak and Mt. Gwangdeoksan radar data were collected from 2010 to 2016 and converted to a gray-scale image file in an HDF5 format with a 1km spatial resolution. The deep neural network model was trained to predict precipitation after 10 minutes by using the four consecutive radar image data, and the recursive method of repeating forecasts was applied to carry out lead time 60 minutes with the pretrained deep neural network model. To evaluate the performance of deep neural network prediction model, 24 rain cases in 2017 were forecast for rainfall up to 60 minutes in advance. As a result of evaluating the predicted performance by calculating the mean absolute error (MAE) and critical success index (CSI) at the threshold of 0.1, 1, and 5 mm/hr, the deep neural network model showed better performance in the case of rainfall threshold of 0.1, 1 mm/hr in terms of MAE, and showed better performance than the translation model for lead time 50 minutes in terms of CSI. In particular, although the deep neural network prediction model performed generally better than the translation model for weak rainfall of 5 mm/hr or less, the deep neural network prediction model had limitations in predicting distinct precipitation characteristics of high intensity as a result of the evaluation of threshold of 5 mm/hr. The longer lead time, the spatial smoothness increase with lead time thereby reducing the accuracy of rainfall prediction The translation model turned out to be superior in predicting the exceedance of higher intensity thresholds (> 5 mm/hr) because it preserves distinct precipitation characteristics, but the rainfall position tends to shift incorrectly. This study are expected to be helpful for the improvement of radar rainfall prediction model using deep neural networks in the future. In addition, the massive weather radar data established in this study will be provided through open repositories for future use in subsequent studies.

Variation Analysis of Distance and Exposure Dose in Radiation Control Area and Monitoring Area according to the Thickness of Radiation Protection Tool Using the Calculation Model: Non-Destructive Test Field (계산 모델을 활용한 방사선방어용 도구 두께에 따른 방사선관리구역 및 감시구역의 거리 및 피폭선량 변화 분석 : 방사선투과검사 분야 중심으로)

  • Gwon, Da Yeong;Park, Chan-hee;Kim, Hye Jin;Kim, Yongmin
    • Journal of the Korean Society of Radiology
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    • v.14 no.3
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    • pp.279-287
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    • 2020
  • Recently, interest in radiation protection is increasing because of the occurrence of accidents related to exposure dose. So, the nuclear safety act provides to install the shields to avoid exceeding the dose limit. In particular, when the worker conducts the non-destructive testing (NDT) without the fixed shielding structure, we should monitor the access to the workplace based on a constant dose rate. However, when we apply for permits for NDT work in these work environments, the consideration factors to the estimation of the distance and exposure dose are not legally specified. Therefore, we developed the excel model that automatically calculates the distance, exposure dose, and cost if we input the factors. We applied the assumption data to this model. As a result of the application, the distance change rate was low when the thickness of the lead blanket and collimator is above 25 mm, 21.5 mm, respectively. However, we didn't consider the scattering and build-up factor. And, we assumed the shape of the lead blanket and collimator. Therefore, if we make up for these limitations and use the actual data, we expect that we can build a database on the distance and exposure dose.

The development of conductive 10B thin film for neutron monitoring (중성자 모니터링을 위한 전도성 10B 박막 개발)

  • Lim, Chang Hwy;Kim, Jongyul;Lee, Suhyun;Jung, Yongju;Choi, Young-Hyun;Baek, Cheol-Ha;Moon, Myung-Kook
    • Journal of Radiation Protection and Research
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    • v.39 no.4
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    • pp.199-205
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    • 2014
  • In the field of neutron detections, $^3He$ gas, the so-called "the gold standard," is the most widely used material for neutron detections because of its high efficiency in neutron capturing. However, from variable causes since early 2009, $^3He$ is being depleted, which has maintained an upward pressure on its cost. For this reason, the demands for $^3He$ replacements are rising sharply. Research into neutron converting materials, which has not been used well due to a neutron detection efficiency lower than the efficiency of $^3He$, although it can be chosen for use in a neutron detector, has been highlighted again. $^{10}B$, which is one of the $^3He$ replacements, such as $BF_3$, $^6Li$, $^{10}B$, $Gd_2O_2S$, is being researched by various detector development groups owing to a number of advantages such as easy gamma-ray discrimination, non-toxicity, low cost, etc. One of the possible techniques for the detection is an indirect neutron detection method measuring secondary radiation generated by interactions between neutrons and $^{10}B$. Because of the mean free path of alpha particle from interactions that are very short in a solid material, the thickness of $^{10}B$ should be thin. Therefore, to increase the neutron detection efficiency, it is important to make a $^{10}B$ thin film. In this study, we fabricated a $^{10}B$ thin film that is about 60 um in thickness for neutron detection using well-known technology for the manufacturing of a thin electrode for use in lithium ion batteries. In addition, by performing simple physical tests on the conductivity, dispersion, adhesion, and flexibility, we confirmed that the physical characteristics of the fabricated $^{10}B$ thin film are good. Using the fabricated $^{10}B$ thin film, we made a proportional counter for neutron monitoring and measured the neutron pulse height spectrum at a neutron facility at KAERI. Furthermore, we calculated using the Monte Carlo simulation the change of neutron detection efficiency according to the number of thin film layers. In conclusion, we suggest a fabrication method of a $^{10}B$ thin film using the technology used in making a thin electrode of lithium ion batteries and made the $^{10}B$ thin film for neutron detection using suggested method.