• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.406.2-406.2
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• 2003

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 추계학술발표대회 요약집
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• pp.490.1-490.1
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• 2003

• 중환자간호학회지
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• 제13권2호
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• pp.12-23
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• 2020

Purpose : This study aimed to evaluate the clinical outcomes of direct interhospital transfers (IHTs) of patients with acute aortic syndrome (AAS) led by advanced practice nurses (APNs). Methods : From September 2014 to June 2017, the study retrospectively investigated 183 patients with AAS who were transferred to a high-volume tertiary hospital. Results : One hundred forty-eight (81%) patients were admitted through direct IHTs, and 35 (19%) patients were admitted through non-direct IHTs. The direct IHT group had a significantly shorter time from symptom onset to hospital arrival than the non-direct IHT group (11.4 vs. 32.1 h, p=.043). There were no significant differences in other clinical outcomes, such as peri-transfer status, mortality, hospital length of stay, and readmission, between the two groups. In the direct IHT group, 55% of transfers were led by APNs. There was no significant difference in outcomes between APN- and physician-led transfers. Conclusions : Implementation of direct IHTs markedly shortened the time from symptom onset to hospital arrival in patients with AAS. Finally, direct IHTs can potentially improve the outcomes of patients with AAS, a condition with time-dependent mortality and morbidity. In addition, APNs can effectively lead the direct IHT of patients with AAS.

• Nuclear Engineering and Technology
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• 제48권4호
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• pp.952-964
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• 2016

The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical characteristics that allow it to violently react with materials such as a water or steam. When a sodium-water reaction (SWR) occurs due to leakage or breakage of steam generator tubes, high-pressure waves and corrosive reaction products are produced, which threaten the structural integrity of the components of the intermediate heat-transfer system (IHTS) and the safety of the primary heat-transfer system (PHTS). In the PGSFR, SWR events are included in the design-basis event. This event should be analyzed from the viewpoint of the integrities of the IHTS and fuel rods. To evaluate the integrity of the IHTS based on the consequences of the SWR, the behaviors of the generated high-pressure waves are analyzed at the major positions of a failed IHTS loop using a sodium-water advanced analysis method-II code. The integrity of the fuel rods must be consistently maintained below the safety acceptance criteria to avoid the consequences of the SWR. The integrity of the PHTS is evaluated using the multidimensional analysis of reactor safety-liquid metal reactor code to model the whole plant.

• 에너지공학
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• 제11권2호
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• pp.122-129
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• 2002

액체금속로의 소듐-물 반응사고에 따른 압력거동 분석을 위하여 한국원자력연구소 KALIMER 개발팀이 개발한 SPIKE코드의 해석 모형 및 알고리즘을 소개하였으며 검증 계산 결과를 제시하였다. KALIMER IHTS의 소듐-물 반응사고로 인한 계통내 압력 거동을 분석하였다. 소듐-물 반응사고의 초기는 압력파 전달과 질량 전달 영역으로 구성됨을 확인하였다. 압력파 전달 영역에서의 압력 거동은 계통의 설계 특성과 무관하나 질량 전달 영역에서는 Cover gas 체적과 파열판 파열 압력에 크게 의존함을 확인하였다. KALIMER IHTS의 초기 소듐-물반응사고 해석 결과는 적절한 Cover gas체적과 파열판 압력 설정을 통해 압력 진동이 설계 압력 범위로 조절할 수 있음을 확인하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 춘계공동학술발표회요약집
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• pp.140.2-140
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• 2002

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.85-86
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• 2005

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.107-114
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• 2016

Four cylindrically shaped IHXs(Intermediate Heat Exchangers) are installed in the PHTS(Primary Heat Transfer System) of the PGSFR(Prototype Gen IV Sodium cooled Fast Reactor). As for the IHX, the temperature difference of structure is inevitable result caused by heat transfer between primary coolant sodium and IHTS(Intermediate Heat Transport System) sodium. It is necessary to evaluate the high temperature structural integrity of IHXs which operate at the elevated temperature condition over the creep temperature. In this paper, the high temperature structural integrity of IHX under assumed loading conditions has been reviewed according to ASME code.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집B
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• pp.386-391
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• 2001

In this paper, the vibration characteristics of IHTS(Intermediate Heat Transfer System) piping system of LMR(Liquid Metal Reactor) conveying hot liquid sodium are investigated to eliminate the pipe supports for economic reasons. To do this, a 3-dimensional straight pipe element and a curved pipe element conveying fluid are formulated using the dynamic stiffness method of the wave approach and coded to be applied to any complex piping system. Using this method, the dynamic characteristics including the natural frequency, the frequency response functions, and the dynamic instability due to the pipe internal flow velocity are analyzed. As one of the design parameters, the vibration energy flow is also analyzed to investigate the disturbance transmission paths for the resonant excitation and the non-resonant excitations.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2007년도 하계학술대회 논문집
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• pp.299-301
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• 2007

본 논문은 무정전 전원공급장치(UPS : Uninterruptible Power Supply System)에서 출력이 중단되는 상황을 최종 출력단에서 감지하여, 첫째 고장 영향의 확산을 차단하고, 둘째 부하에 무정전의 전원공급을 실시할 수 있도록 하는 고속절환장치에 관한 것이다. 본 시스템은 기존 UPS 시스템이 가지고 있는 출력전원을 검출하여 기준전압 범위에서 벗어나면 절체 시키는 일반적인 방식이 아니라, 별도의 시스템을 UPS와는 독립적으로 구성하여 UPS 내부 사고시 고장이 부하와 계통상에도 영향을 주는 현상을 차단하기 위하여 절체 시점에서의 이상적인 접점 상태를 고려하고, UPS의 모든 제어시스템이 불가능한 시점에서도 부하의 연속성을 보장할 수 있도록 구성한 독립제어 고속절환장치 개발에 관한 논문이다.