• Journal of Korean Academy of Nursing
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• v.22 no.2
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• pp.248-259
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• 1992

질적 보장은 전문직 종사자에 의하여 수혜받는 대상자를 보호하기 위하여 전적으로 필요한 프로그램이다. 이러한 질적보장을 통하여 전문직의 자율성과 책임을 튼튼히 할 수 있는 의무는 전문직 종사자 모두의 관심사가 되어야 한다. 미국에 있어서 질적 간호에 대한 관심은 이제 새로운 이유가 아니다. Beyers(1988)는 건강체계 지도자 사이에 가장 중요한 문제로 강조하는 것이 수혜자의 이용의 용이성(Access), 숫가(Cost) 그리고 질적인 제공(Quality)이 라고 피력 하였다. 미국 건강사업 평가자와 조정자(Regulator)들은 질(Quality)을 위한 자율적인 프로그램에 많은 에너지를 투입하여 전반적인 건강사업 즉 의료계의 질보장, 더 나아가서는 간호의 질을 향상 시키기 위한 많은 프로그램을 분석 연구한다. 이 논문은 간호에 있어서 질적 보장을 위한 내용으로 주요점은 질적 보장에 사용되는 용어, 역사적 배경, 질적 보장을 강조하는 이유, 질적 보장제도의 개발, 질 사정(euali assessment)과 질적 보장에 있어서 간호 전문직 개입을 차례대로 설명하였다. 구미의 경우 1970년대부터 간호직에 있어서는 질적보장제도개발에 우선순위를 두게되어 미 간호협회에서는 Professional Standards Review Organizations (PSRO)에 근거하여 간호실무를 위한 표준을 내어놓았다. 질적보장을 위한 평가방법으로 구조, 과정, 결과 그리고 수혜자가 간호계획을 세우는데 사정에 참여하는 방법 등 4가지를 간략하게 설명하였다. 질적 보장을 향상시키기 위해서는 전문직과 공공의료기간이 서로 협동체가 되어 중추역할을 해야함을 강조하고 이렇게 서로 협력하므로써만이 비로서 우리의 목적을 성취할 수 있다고 생각된다.구 등이 이용된다. $^{166}$ Ho, $^{198}$ Au, $^{32}$P, $^{90}$ Y, $^{169}$ Er, $^{186}$ Rc, $^{131}$ I, $^{211}$ At 등 의 방사성 핵종의 교질, 미소구 또는 단세포군 항체표지 형태로 직접 종양내 또는 공동이나 체강에 투여하는 치료법이 있다. 류마치스 관절염의 슬관절에 $^{165}$ Dy colloid를 주사하는 $^{166}$ Ho-MAA도 활발히 이용되고 있다. and computed groundwater levels. 본 논문에서는 가파른 산사면에서 산사태의 발생을 예측하기 위한 수문학적 인 지하수 흐름 모델을 개발하였다. 이 모델은 물리적인 개념에 기본하였으며, Lumped-parameter를 이용하였다. 개발된 지하수 흐름 모델은 두 모델을 조합하여 구성되어 있으며, 비포화대 흐름을 위해서는 수정된 abcd 모델을, 포화대 흐름에 대해서는 시간 지체 효과를 고려할 수 있는 선형 저수지 모델을 이용하였다. 지하수 흐름 모델은 토층의 두께, 산사면의 경사각, 포화투수계수, 잠재 증발산 량과 같은 불확실한 상수들과 a, b, c, 그리고 K와 같은 자유모델변수들을 가진다. 자유모델변수들은 유입-유출 자료들로부터 평가할 수 있으며, 이를 위해서 본 논문에서는 Gauss-Newton 방법을 이용한 Bard 알고리즘을 사용하였다. 서울 구로구 시흥동 산사태 발생 지역의 산사면에 대하여 개발된 모델을 적용하여 예제 해석을 수행함으로써, 지하수 흐름 모델이 산사태 발생

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.88-94
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• 1996

원자력발전소의 공조계통에 설치되어 운영되는 기체 방사성물질 제거용 첨착 활성탄 탑내에서 균일한 공기 유속분포가 유지되고 있는지를 확인하기 위한 실험을 실시하였다. 본 실험에 사용되는 장비(Tester for Flow Distribution, 이하 TFD라 함)는 원자력발전소에서 사용하는 첨착 활성탄 필터(Adsorber)내의 흡착층을 모방하여 자체에서 제작하였으며, 시험조건들은 실제의 값을 기준으로 적용하였다. 각 위치에서의 보정된 용적 유속을 구하기 위해 자체에서 만든 "FLOWD"라는 계산프로그램을 사용하였으며, 입구 및 출구측 공간에 10" 간격으로 각 6개씩 유속 감지기를 설치하여 면속도를 구하였다. 각 지점에서의 면속도는 평균 0.24449m/s로 각 구간에서의 겉보기 면속도의 분포는 매우 균일한 값을 나타내었으며, 약 2% 이내의 편차로 활성탄 탑내에서의 공기의 흐름이 균일하게 통과함을 확인할 수 있었다.통과함을 확인할 수 있었다.

• Tunnel and Underground Space
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• v.31 no.5
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• pp.333-359
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• 2021

Gases such as hydrogen and radon can be generated around the canister in high-level radioactive waste disposal systems due to several reasons including the corrosion of metal materials. When the gas generation rate exceeds the gas diffusion rate in the low-permeability bentonite buffer, the gas phase will form and accumulate in the engineered barrier system. If the gas pressure exceeds the gas entry pressure, gas can migrate into the bentonite buffer, resulting in pathway dilation flow and advective flow. Because a sudden occurrence of dilation flow can cause radionuclide leakage out of the engineered barrier of the radioactive waste disposal system, it is necessary to understand the gas migration behavior in the bentonite buffer to quantitatively evaluate the long-term safety of the engineered barrier. Experimental research investigating the characteristics of gas migration in saturated bentonite and research developing numerical models capable of simulating such behaviors are being actively conducted worldwide. In this technical note, previous gas injection experiments and the numerical models proposed to verify such behaviors are introduced, and the future challenges necessary for the investigation of gas migration are summarized.

• Tunnel and Underground Space
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• v.33 no.4
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• pp.228-243
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• 2023

Bentonite is widely recognized and utilized as a buffer material in high-level radioactive waste repositories, mainly due to its favorable characteristics such as swelling capability and low permeability. Bentonite buffers play an important role in ensuring the safe disposal of radioactive waste by providing a low permeability barrier and effectively preventing the migration of radionuclides into the surrounding rock. However, the long-term performance of bentonite buffers still remains a subject of ongoing research, and one of the main concerns is the erosion of the buffer induced by swelling and groundwater flow. The erosion of the bentonite buffer can significantly impact repository safety by compromising the integrity of buffer and leading to the formation of colloids that may facilitate the transport of radionuclides through groundwater, consequently elevating the risk of radionuclide migration. Therefore, it is very important to numerically quantify the erosion of bentonite buffer to evaluate the long-term performance of bentonite buffer, which is crucial for the safety assessment of high-level radioactive waste disposal. In this technical note, Two-region model is introduced, a proposed model to simulate the erosion behavior of bentonite based on a dynamic bentonite diffusion model, and quantitative evaluation is conducted for the bentonite buffer erosion with this model.

• Journal of the Korean Society of Systems Engineering
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• v.17 no.1
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• pp.65-75
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• 2021

When the decommissioning of South Korea nuclear power plants is promoted in earnest with the permanent shutdown of Kori Unit 1 in 2017, a large amount of various types of radioactive waste will be generated. For minimal generation and safe management of decommissioning waste, the waste should be made by appropriate classification of the dismantling waste characteristics in accordance with physical, chemical and radiological characteristics to meet the acceptance criteria of disposal facilities. Replacing the preliminary inspection at the site for the compliance of the waste acceptance criteria (WAC) of medium and low-level radioactive waste with the generator's own radioactive waste certification program (WCP), from the perspective of disposal, the optimization of waste management at the national level contributes to the efficient availability of disposal, such as the processing of non-conforming radioactive wastes at the site. To this end, it is important to evaluate radioactivity in each system and area such as nuclear reactors before decommissioning is carried out in earnest, and the prior removal of harmful wastes is important. From waste collection to waste disposal, decommissioning waste should be managed at each stage in consideration of the acceptance criteria of disposal facilities to minimize the generation of non-conforming waste.

• 한국공간정보시스템학회:학술대회논문집
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• 2004.05a
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• pp.255-263
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• 2004

광명시 경륜 경기장은 국민 체육진흥공단에서 턴키(Turn key)공사로 발주하였고, CS구조+공간건축+대우건설, 삼성건설, 태영건설의 제출안이 당선되어 현재 시공중에 있다. 경기장의 저층부는 PC로 설계되었고, 지붕은 철골 트러스를 사용한 Dome 형상으로 이루어져 있다. 돔 지붕의 개념은 지붕에 물을 부었을 때 가장 흘러가기 쉬운 방향으로 트러스를 배치하여 유연한 힘의 흐름을 유도하는 것이다. 143.6m(폭)${\times}$183.5m(길이)${\times}$21m(높이)의 지붕엔 지붕의 개념인 Flow Truss를 물이 흐르는 방향의 방사형으로 배치하고, 내부에 압축링(Compression Ring Truss)과 외부에 인장링(Tension Ring Truss)를 설치하여 힘의 흐름을 단순화시켰고, 실내에서 보기에 플로우 트러스의 간격을 넓게 유지함으로써 개방감을 극대화시켰다. 또한 Flow Truss는 동일한 곡률과 길이로 설계하여 표준화시킴으로써 시공성과 경제성을 동시에 만족토록 하였다. 현재 저층부 시공은 거의 완료된 상황이고, 곧 지붕을 설치할 예정이다. 본 고에서는 돔 지붕의 형성 개념과 설계 과정을 살펴보고, 접합상세 등의 해결에 대해 살펴보겠다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.1
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• pp.45-63
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• 2017

The oldest commercial reactor in South Korea, Kori-1 Nuclear Power Plant (NPP), will be shut down in 2017. Proper treatment for decommissioning wastes is one of the key factors to decommission a plant successfully. Particularly important is the recycling of clearance level or very low level radioactively contaminated metallic wastes, which contributes to waste minimization and the reduction of disposal volume. The aim of this study is to introduce a conceptual design of a recycle system and to evaluate the doses incurred through defined work flows. The various architecture diagrams were organized to define operational procedures and tasks. Potential exposure scenarios were selected in accordance with the recycle system, and the doses were evaluated with the RESRAD-RECYCLE computer code. By using this tool, the important scenarios and radionuclides as well as impacts of radionuclide characteristics and partitioning factors are analyzed. Moreover, dose analysis can be used to provide information on the necessary decontamination, radiation protection process, and allowable concentration limits for exposure scenarios.

• Journal of radiological science and technology
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• v.36 no.1
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• pp.49-55
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• 2013

Currently, commercially available phantom can reproduce and evaluate only a static situation, the study is incomplete research on phantom and system which is can confirmed functional situation in the kidney by time through dynamic phantom and blood flow velocity, various difference according to the amount of radioactive. Therefore, through this study, it has produced the dynamic kidney phantom to reproduce images through the dynamic flow of the kidney, it desires to evaluate the usefulness of nuclear medicine imaging. The production of the kidney phantom was fabricated based on the normal adult kidney, in order to reproduce the dynamic situation based on the fabricated kidney phantom, in this study, it was applied the volume pump that can adjust the speed of blood flow, so it can be integrated continuously radioactive isotopes in the kidney by using $^{99m}Tc$-pertechnate. Used the radioactive isotope was supplied through the two pump. It was confirmed the changes according to the infusion rate, radioactive isotopes and the different injection speeds on the left and right, analysis of the acquired images was done by drawn five times ROI in order to check the reproducibility of each on the front and rear of the kidney and bladder. Depending on the speed of injection, radioisotope was a lot of integrated and emissions up when adjusting the pressure of the pump as 30 stroke, it was the least integrated and emissions up when adjusting as 40 stroke. The integration of the left & right kidney was not reached in the amount of the highest when adjusting as 10 stroke. In the changes according to the amount of the radioactive isotope, 0.6 mCi(22.2 MBq), 0.8 mCi (29.6 MBq)was showed up similar tendency but, in the result of the different injection 0.8 mCi, it was showed up counts close to double of 0.6 mCi. In the result of the differently injection speed of the left & right kidney, as a result of different conditions that injection speed was 20 stroke through left kidney phantom, the injection speed was 30 stroke through right kidney phantom, it was enough difference in the resulting image can be easily distinguished with the naked eye. Through this study, the results showed that the dynamic kidney phantom system is able to similarly reproduce renogram in the actual clinical practice. Especially, the depicted over time for the flow to be excreted through the kidney into the bladder was adequately reproduce, it is expected to be utilized as basic data to check the quality of the dynamic images. In addition, it is considered to help in the field of functional imaging and quality control.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.265-282
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• 2008

Based on the site characterization works in a low and intermediate level waste(LILW) repository site, the numerical simulations for groundwater flow were carried out in order to understand the groundwater flow system of repository site. To accomplish the groundwater flow modeling in the repository site, the discrete fracture network(DFN) model was constructed using the characteristics of fracture zones and background fractures. At result, the total 10 different hydraulic conductivity(K) fields were obtained from DFN model stochastically and K distributions of constructed mesh were inputted into the 10 cases of groundwater flow simulations in FEFLOW. From the total 10 numerical simulation results, the simulated groundwater levels were strongly governed by topography and the groundwater fluxes were governed by locally existed high permeable fracture zones in repository depth. Especially, the groundwater table was predicted to have several tens meters below the groundwater table compared with the undisturbed condition around disposal silo after construction of underground facilities. After closure of disposal facilities, the groundwater level would be almost recovered within 1 year and have a tendency to keep a steady state of groundwater level in 2 year.

• Journal of Korean Society of Environmental Engineers
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• v.39 no.5
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• pp.282-287
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• 2017

The purpose of this study was predicted the effects of mixing and diffusion due to the operation of the apparatus before the development of the mixed diffusion device for the decontamination absorbent to minimize the influence of contaminant inflow due to radiation accident. The tracer used for the flow characteristics was $^{68}Ga$, $^{99m}Tc$, which is a radioactive isotope, and 2 inch NaI radiation detector was used to detect it. The impeller of the decontamination mixed diffusion system applied to this study was made into three types and the mixing diffusion effect was compared. As a result of analyzing the flow characteristics of the radio-isotope with decontamination mixed diffusion device, mixing, diffusion and flow pattern were obtained. The radial mixing type impeller was able to diffuse to the water surface by the upflow flow, and the fin structure was adjusted for finding optimal conditions. The model 3 type consists of a fin guiding part and an auxiliary fin so that the diffusion speed is higher than that of other types of impellers. It also showed a short time to reach complete mixing.