• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 춘계공동학술발표회요약집
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• pp.188.2-188
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• 2002

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.675-676
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• 2005

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.134-140
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• 2016

The Control Rod Assembly (CRA) controls the reactor power by adjusting its position in the reactor core during normal operation and should be quickly inserted into the reactor core by free drop under scram condition to shut down chain reactions. Therefore, the drop time of the CRA is one of important factors for the safety of the nuclear reactor and must be experimentally verified. This study presents the drop performance test of the CRA which has been conceptually designed for the Proto-type Generation IV Sodium-cooled Fast Reactor. During the test, the CRA was free dropped from a height of 1 m under different flow rate conditions and its drop time was measured. The results showed that the drop time of the CRA increased as the flow rate increased; the average drop times of the CRA were approximately 1.527 seconds, 1.599 seconds and 1.676 seconds at 0%, 100% and 200% of design flow rates, respectively.

• 대한전자공학회논문지
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• 제13권1호
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• pp.1-10
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• 1976

원자로의 안전계통에 이용되는 2-out of-3 내시회로 및 파고선별기에 관해 인술하고 상세한 해석을 하였다. 1-out of-m 동시회로의 안전신뇌도 및 확사비상정지신뇌도에 관한 식을 유도하여 적정한 1의 값을 구하였다. 2-out of-3 동시유로는 펄스 합산 방법을 이용하여 설계하였으며 매우 간단한 원리로 동작한다. 파고선별기는 전 선렬영역에 걸쳐 좋은 직선성 및 threshold 안정도를 가진다. A 2-out of-3 coincidence circuit and a discriminator to be used in the safely systems in nuclear reactors are described and analyzed in detail. The expressions for the reliability and the spurious scram reiliability of 1·out of-m coincidence logic in general are derived and the optimum value of 1 is assessed. The coincidence circuit is designed by making use of the pulse-summing method and is very simple in principle. The discriminator has good linearity in in the whole discrimination range and good threshold stability.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2017년도 제48회 춘계학술대회논문집
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• pp.297-300
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• 2017

스크램에서 램제트로의 천이가 일어날 때, thermal choking으로 인한 연소실 입구에서의 급격한 압력 상승은 불가피하다. NAR이라고도 불리는 이러한 현상은 당량비의 과도한 증가에 의해서 관찰된다. 그러나, NAR의 변화에 영향을 미치는 요소들에 대한 연구는 활발하게 이루어지지 않았다. 본 연구에서는 격리부 입구에서의 마하수에 따른 NAR의 변화는 수치해석적 그리고 이론해석적으로 분석되었다. 결론적으로 격리부 입구의 마하수 증가는 NAR의 범위를 확대시킨다.

• 시스템엔지니어링학술지
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• 제16권2호
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• pp.47-58
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• 2020

Most of the reactor trips in Korean NPPs related to core protection systems were caused not because of proximity of boiling crisis and, consequently, a damage in the core, but due to particular miscalculations or component failures related to the core protection system. The most common core protection system applied in Korean NPPs is the Core Protection Calculator System (CPCS), which is installed in OPR1000 and APR1400 plants. It generates a trip signal to scram the reactor in case of low Departure from Nucleate Boiling Ratio (DNBR) or high Local Power Density (LPD). However, is a reactor trip necessary to protect the core? Or could a fast power reduction be enough to recover the DNBR/LPD without a scram? In order to analyze the online calculation of DNBR/LPD, and the use of fast power reduction as trip avoidance methodology, a concept of CPCS with fast power reduction function was developed in Matlab® Simulink using systems engineering approach. The system was validated with maximum of 0.2% deviation from the reference and the dynamic deviation was maximum of 12.65% for DNBR and 6.72% for LPD during a transient of 16,000 seconds.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4601-4619
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• 2022

The classical Probabilistic Safety Analysis (PSA) does not include any time dependence explicitly. However, the success criteria (SC) could evolve during the cycle for some initiating events. In that sense, there is a type of sequence in which this time-dependency is quite important, the family of Anticipated Transient without Scram (ATWS) sequences in Pressurized Water Reactors. Therefore, a new risk-informed approach is proposed in this paper, which makes it possible to obtain the time-dependent SC evolution of the safety functions affected by the Moderator Temperature Coefficient (MTC) value. Then, the evolution of the ATWS conditional core damage probability (CCDP) could be obtained using a PSA model. To quantify the CCDP, the average values of the time-dependent failure probabilities must be computed. Finally, the comparison between the CCDP obtained through the application of the classical PSA approach and the new one makes it possible to quantify the impact of time-dependence on the SC of the headers that this new risk-informed ATWS approach can provide.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.489-494
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• 1997

A comparative transient analyses were performed for oxide and nitride cores or a large (3000 MWt), pool-type, liquid-metal-cooled reactor (LMR). The study was focused on three representative accident initiators with failure to scram : the unprotected loss-of-flow (ULOF), the unprotected transient overpower (UTOP), and the unprotected fast transient overpower (UFTOP). The margins to fuel melting and sodium boiling have been evaluated for these representative transients. The results show that there is an increase in safety margin with nitride core which maintains the physical dimensions of the oxide core.

• 한국콘텐츠학회논문지
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• 제10권2호
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• pp.54-62
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• 2010

역파일 인덱스 구조는 대용량 텍스트 데이터의 색인저장 기법을 위한 효율적인 데이터 구조로 널리 활용 되고 있다. 특히, 최근 이슈가 되고 있는 온라인 색인관리 측면에서는 동적 검색 환경에 적합한 In-Place 방식과 Merge-based 색인 방식이 주로 사용 되고 있다. 위 방법들의 핵심은 검색 처리시간을 줄이기 위해서 포스팅 정보의 저장 연속성(Contiguity)을 보장하면서 동시에 색인정보 관리(Index Maintenance) 시간을 최소화 하기위한 색인저장 구조에 중점을 두고 연구가 진행 되었다. 그러나 최근 기존 저장장치(HDD)와 근본적으로 구조가 다른 새로운 저장장치(SSD, SCRAM)가 데이터 저장소로 이용되면서 이러한 장치들의 특성을 효과적으로 활용할 수 있는 새로운 형태의 색인저장 기법 또한 필요하게 되었다. 따라서 본 논문에서는 새로운 저장장치의 빠른 접근 속도(Low access latency) 특성을 최대한 활용할 수 있는 분할(Segmentation) 포스팅 구조를 기반으로 새로운 저장장치에 적합하도록 변형된 In-Place 방식(Pulsing)과 수정된 Merge-based 방식(Merging)을 혼합하여 검색 처리시간 및 색인정보관리시간을 크게 향상시킬 수 있는 새로운 색인저장 구조(SPM)를 제안한다.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2004년도 제22회 춘계학술대회논문집
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• pp.75-78
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• 2004

Various jet engines (Turbine engine family and RAM Jet engine) have been developed for high speed aircrafts. but their application to hypersonic flight is restricted by principle problems such as increase of total pressure loss and thermal stress. Therefore, the development of next generation propulsion system for hypersonic aircraft is a very important subject in the aerospace engineering field, SCRAM Jet engine based on a key technology, Supersonic Combustion. is supposed as the best choice for the hypersonic flight. Since Supersonic Combustion requires both rapid ignition and stable flame holding within supersonic air stream, much attention have to be given on the mixing state between air stream and fuel flow. However. the wider diffusion of fuel is expected with less total pressure loss in the supersonic air stream. So. in this study the direction of fuel injection is inclined 30 degree to downstream and the total pressure of jet is controlled for lower penetration height than thickness of boundary layer. Under these flow configuration both streams, fuel and supersonic air stream, would not mix enough. To spread fuel wider into supersonic air an aerodynamic force, baroclinic torque, is adopted. Baroclinic torque is generated by a spatial misalignment between pressure gradient (shock wave plane) and density gradient (mixing layer). A wedge is installed in downstream of injector orifice to induce an oblique shock. The schlieren optical visualization from side transparent wall and the total pressure measurement at exit cross section of combustor estimate how mixing is enhanced by the incidence of shock wave into supersonic boundary layer composed by fuel and air. In this study non-combustionable helium gas is injected with total pressure 0.66㎫ instead of flammable fuel to clarify mixing process. Mach number 1.8. total pressure O.5㎫, total temperature 288K are set up for supersonic air stream.