• Proceedings of the Korean Vacuum Society Conference
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• 2010.08a
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• pp.47-47
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• 2010

게이트 밸브는 진공 시스템 구성에 있어서 빠질 수 없는 중요한 부품 중 하나로 공간을 구획하여 필요에 따라 자유롭게 진공 상태와 대기 개방 상태가 공존하도록 만들어 주며 진공펌프와 같은 주요 기기들의 탈착 및 교체를 용이하게 해 준다. 게이트 밸브는 열린 상태에서는 저항이 최소화되는 반면 닫힌 상태에서는 마치 마구리 플랜지로 막은 것처럼 완벽한 차단이 요구된다. 일반적으로 게이트 밸브 상용제품은 개스킷이 닿는 밸브 시트가 한쪽에만 마련되어 있으므로 디스크 기계구조가 충분한 압력을 발휘하지 못한다면 어느 쪽이 대기압인가에 따라 디스크를 미는 힘의 크기가 변하여 기밀특성이 달라질 수 있다. 따라서 게이트 밸브의 누설검사는 순방향과 역방향 모두에 대해 시행해야 한다. 양방향 누설검사를 위해 한쪽 밸브 공간을 배기하고 반대쪽 공간에 헬륨을 뿌리는 작업을 교대로 하려면 배기시간의 단축과 신속한 잔류 헬륨기체 제거가 필수적이다. 게이트 밸브 제조 공장에서 상품을 출하하기 위한 시험검사라는 것을 전제로 합리적인 시간 내에 정확한 누설검사를 일관성 있게 할 수 있는 적절한 누설검사 시스템을 설계하고 측정절차를 상용 게이트 밸브에 대해 적용해 보았다.

• Proceedings of the Korea Water Resources Association Conference
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• 2019.05a
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• pp.7-7
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• 2019

중요한 사회기반시설물 중 하나인 상수관망시스템은 대부분의 시설물이 지중에 매설되어있기 때문에 지진에 취약하고 복구에 어려움이 크며, 지진 발생 시 대규모 피해로 이어질 우려가 있다. 따라서 상수관망시스템에 대한 지진피해를 최소화하고 재해로부터 신속하게 복구하기 위한 적절한 복구전략을 마련할 필요가 있다. 상수관로에 발생하는 지진피해는 크게 파손과 누수로 구분되며, 대구경 관로가 파손될 경우 대규모 단수 및 피해가 우려되므로 신속한 복구전략이 마련되어야한다. 일반적으로 파손 관로의 복구는 먼저 피해 관로 인근의 제수밸브의 차폐를 통해 통수를 차단한 후 교체 작업을 진행하는 것이 일반적이며, 해당 과정에서 밸브 차폐에 의한 단수구역의 발생이 불가피하다. 이러한 단수구역 발생은 해당 지역의 용수공급능력 저하로 이어지며, 단수구역의 범위 및 단수용량의 규모는 제수밸브의 위치 및 개수에 따라 결정된다. 본 연구에서는 기개발된 상수관망 지진피해복구 시뮬레이션 모형(Choi et al., 2018)을 개선하여 지진피해복구 시 시스템 내 제수밸브의 설치 위치와 개수에 따라 발생되는 단수구역과 단수상황이 상수관로의 용수공급능력(Serviceability)에 미치는 영향을 분석하였다. 개선된 모형은 피해복구에 따른 용수공급능력을 정량적으로 산정할 수 있으며, 피해 관로의 복구 시 제수밸브 차폐에 의해 발생되는 단수구역을 탐색한 후, 수리해석 모의에 적용함으로써 현실적인 용수공급 상황을 모의할 수 있도록 개선되었다. 또한, EPANET3.0의 Full-PDA(Pressure driven analysis)를 이용함으로써 지진과 같은 비정상상황(다수관의 파손에 따른 압력저하)에서 좀 더 현실적인 수리해석이 가능하도록 개선되었다. 본 연구에서는 해당모형을 실제관망에 적용하여 제수밸브 설치개수 및 위치가 지진피해복구에 미치는 영향을 비교 분석하였으며, 또한 효율적인 지진피해복구 방안을 제시하였다.

• Journal of Radiation Protection and Research
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• v.35 no.2
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• pp.57-62
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• 2010

Maintenance on the water chamber of steam generator, the change of pressurizer heater, the removal of pressure tube feeder, and so on during outage in nuclear power plants (NPPs) has a likelihood of high radiation exposure to whole body of workers even short time period due to the high radiation exposure rates. In particular, it is expected that hands would receive the highest radiation exposure because of its contact with radiation materials. In this study, field tests on extremity dose assessment of radiation workers for contact works with high radiation exposure were conducted during the maintenance periods in Korean pressurized water reactors (PWRs) and pressurized heavy water reactors (PHWRs). In this field test, radiation workers were required to wear additional TLDs on the back and wrist, and an extremity dosimeter on fingers including a main TLD on the chest, while performing maintenance. As a result, it was found that the equivalent dose for fingers was distributed in the fixed range of deep dose and the equivalent dose for wrists.

• The Journal of the Korea Contents Association
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• v.19 no.11
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• pp.445-450
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• 2019

This study proves that syringe reuse of automated injection system entails a risk of contrast media reflux and saline solution contamination which are pumped by a piston into the patients' venous cannula in the dynamic MR images, we will be aware of the serious problem. To quantify the contrast media contamination effect on the saline solution, identical volume of the saline solution was collected before and after the contrast injection to the patients' venous cannula following T1 weighted image scanning to verify whether signal intensities differences are observed. The signal intensity of saline solution after the contrast injection was significantly higher than that of saline before injection by 523.43%. This result is due to the backflow that contaminates the saline solution on the opposite side when the contrast agent is injected. In conclusion, the syringe used to inject contrast medium. causes cross-contamination due to contrast reflux. Therefore, even if the same patient's examination is used for quantitative analysis, the error should be avoided by changing the acquisition sequence or replacing the syringe.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.13 no.3
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• pp.1255-1262
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• 2012

Look into the nuclear power plant of Wolsong currently, it is controlled in order to required operating pressure with PI controller. PI controller has a simple structure and satisfy design requirements to gain setting. However, It is difficult to control without changing the gain from produce changes in parameters such as loss of the valves and the pipes. To solve these problems, the dynamic change of the PI controller gain, or to compensate for the PI controller output is desirable to configure the controller. The aim of this research and development in the parameter variations can be controlled to a stable controller design which is reduced an error and a vibration. Proposed PI/NN control techniques is the PI controller and the neural network controller that combines a parallel and the neural network controller part is compensated output of the controller for changes in the parameters were designed to be robust. To directly evaluate the controller performance can be difficult to test in real processes to reflect the characteristics of the process. Therefore, we develope the simulator model using the real process data and simulation results when compared with the simulated process characteristics that showed changes in the parameters. As a result the PI/NN controller error and was confirmed to reduce vibrations.

• Journal of Radiation Protection and Research
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• v.28 no.3
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• pp.207-213
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• 2003

Carbon-14 is one of the major radionuclides released by CANDU Nuclear Power Plants(NPPs). It is almost always emitted as gas through the stack. From CANDU NPPs about 95% of all carbon-14 is released as carbon dioxide. Carbon-14 is a low energy beta emitter which, therefore, gives only a small skin dose from external radiation. As carbon dioxide Is physiologically rather inert gases for man's metabolism, the inhalation dose is probably less than 1 % of the ingestion dose. But this source of carbon-14, formed in a closed, nor-oxidative environment, was subsequently released into the workplace as an insoluble particulate when these systems were opened lip for re-tubing at CANDU NPPs. As a part of the improvement of dosimetry program at Wolsong Nuclear Power Plants, the carbon-14 metabolism based on references was investigated and studied to setup the internal dosimetry program due to inhalation of carbon-14.

• Journal of Radiation Protection and Research
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• v.34 no.4
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• pp.176-183
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• 2009

Maintenance on the water chamber of steam generator during outage in nuclear power plants (NPPs) has a likelihood of high radiation exposure to whole body of workers even short time period due to the high radiation exposure rates. In particular, it is expected that hands would receive the highest radiation exposure because of its contact with radiation materials. In this study, characteristic analysis of inhomogeneous radiation fields for contact operations was conducted using thermoluminescent dosimeter (TLD) readouts from the application tests of two-dosimeter algorithm to Korean NPPs in 2004. It is regarded that inhomogeneous radiation fields for contact operations in NPPs are dominated by high energy photons. In addition, field tests for workers who participated in maintenance on the steam generator during outage at Ulchin NPPs in 2009 and pressure tube replacement at Wolsong NPPs in 2009 were conducted to analyze radiation fields and to estimate the extremity dose. As a result, radiation fields were dominated by high energy photons.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.21-34
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• 2015

Source term analysis should be carried out to prepare the decommissioning of the nuclear power plant. In the planning phase of decommissioning, the classification of decommissioning wastes and the cost evaluation are performed based on the results of source term analysis. In this study, the verification of MCNP/ORIGEN-2 model is carried out for preliminary source term calculation for Wolsung Unit 1. The inventories of actinide nuclides and fission products in fuel bundles with different burn-up were obtained by the depletion calculation of MCNPX code modelling the single channel. Two factors affecting the accuracy of source terms were investigated. First, the neutron spectrum effect on neutron induced activation calculation was reflected in one-group microscopic cross-sections of relevant radio-isotopes using the results of MCNP simulation, and the activation source terms calculated by ORIGEN-2 using the neutron spectrum corrected library were compared with the results of the original ORIGEN-2 library (CANDUNAU.LIB) in ORIGEN-2 code package. Second, operation history effect on activation calculation was also investigated. The source terms on both pressure tubes and calandria tubes replaced in 2010 and calandria tank were evaluated using MCNP/ORIGEN-2 with the neutron spectrum corrected library if the decommissioning wastes can be classified as a low level waste.