• Nuclear Engineering and Technology
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• 제13권2호
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• pp.63-72
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• 1981

핵연료 집합체의 예기치 않은 파손으로 인하여 설계 근거 재장전 방침이 변경되면 원자로심내에서의 출력 분포 비균형을 막기 위하여 파손된 핵연로 집합체 이외에 대칭 위치의 집합체도 제거되어야 할 경우가 있다. 이와 같은 때에 제거된 핵연료 집합체가 설계연소도에 미달되는 경우 이를 다시 사용하여 핵연료 이용률을 증진시키는 것이 연구되었다. TDCORE 코드가 노심ㆍ해석을 위해 이용되었으며, 최적장전모형을 찾는 코드로는 RELOAD-II가 이용되었다. 고리 1호기에 적용한 결과, 제 1주기말에 제거된 비교적 적게 연소된 4개의 핵연료집합체를 제 3주기에서 이용할 경우 주기 연소도가 l1648 MWD/MTU(가동율 : 80%)에 이를 수 있음을 알 수 있었으며 평형주기까지의 장전모형을 추적하였다.

• 대한기계학회논문집A
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• 제30권9호
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• pp.1041-1048
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• 2006

The pulley is one of core mechanical elements in the power steering system for vehicles. The pulley operates under both the compressive loading and the torque. Therefore, to assure the safety of the power steering system, it is very important to investigate the durability and the optimization of the pulley. In this study, the applied stress distribution of the pulley under high tension and torsion loads was obtained by using finite element analysis. Based on these results the fatigue life of the pulley with the variation of the fatigue strength was evaluated by a durability analysis simulator. The results at 50% and 1% for the failure probability were compared with respect to the fatigue life. In addition to the optimum design for the fatigue life is obtained by the response surface method. The response function utilizes the function of the life and weight factors. Within range for design life condition the minimization of the weight, one of the formulation, is obtained by the optimal design. Moreover the optimum design by considering its durability and validity is verified by the durability test.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.532-548
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• 2021

Nuclear power plants contain several monitoring systems that can identify the in-vessel phenomena of a severe accident (SA). Though a lot of analysis and research is carried out on SA, right from the development of the nuclear industry, not all the possible circumstances are taken into consideration. Therefore, to improve the efficacy of the safety of nuclear power plants, additional analytical studies are needed that can directly monitor severe accident phenomena. This paper presents an interacting multiple model (IMM) based fault detection and diagnosis (FDD) approach for the identification of in-vessel phenomena to provide the accident propagation information using reactor vessel (RV) out-wall temperature distribution during severe accidents in a nuclear power plant. The estimation of wall temperature is treated as a state estimation problem where the time-varying wall temperature is estimated using IMM employing three multiple models for temperature evolution. From the estimated RV out-wall temperature and rate of temperature, the in-vessel phenomena are identified such as core meltdown, corium relocation, reactor vessel damage, reflooding, etc. We tested the proposed method with five different types of SA scenarios and the results show that the proposed method has estimated the outer wall temperature with good accuracy.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4226-4230
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• 2022

The Korea Atomic Energy Research Institute (KAERI) has designed a Hybrid-Low Power Research Reactor (H-LPRR) which can be used for critical assembly and conventional research reactor as well. It is an open tank-in-pool type research reactor (Thermal Power: 50 kW_th) of which the most important applications are Neutron Activation Analysis (NAA), Radioisotope (RI) production, education and training. There are eight irradiation holes on the edge of the reactor core: IR (6 holes for RI production) and NA (2 holes for NAA) holes. In order to quantify the elemental concentration in target samples through the Instrumental Neutron Activation Analysis (INAA), it is necessary to measure neutron spectrum parameters such as thermal neutron flux, the deviation from the ideal 1/E epithermal neutron flux distribution (α), and the thermal-to-epithermal neutron flux ratio (f) for the irradiation holes. In this study, the MCNP6.1 code and FORTRAN 90 language are applied to determine the parameters for the two irradiation holes (NA-SW and NA-NW) in H-LPRR, and in particular its α and f parameters are compared to values of other research reactors. The results confirmed that the neutron irradiation holes in H-LPRR are designed to be sufficiently applied to neutron activation analysis, and its performance is comparable to that of foreign research reactors including the TRIGA MARK II.

• 한국전자통신학회논문지
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• 제15권3호
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• pp.413-420
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• 2020

군 전술정보통신체계(TICN: Tactical Information and Communication Network)는 이동기지국시스템(MSAP: Mobile Subscriber Access Point)을 활용하여 음성 및 데이터 등 실시간 멀티미디어 서비스를 제공한다. 이때 소용량 무선전송체계와 대용량 무선전송체계를 통해 외부전송로를 구성하게 된다. 각 무선전송체계의 통신기기들은 전술차량에 탑재되고 전술차량에 공급전원이 통합전원제어장치로 절체 될 때 전원차단을 예방하기 위해 2차전지가 사용된다. 본 논문은 이동기지국시스템 통합제어장치 배터리 충전용 무선전력전송기기를 장하분배법을 이용하여 기본 설계하고 공극에 의한 설계 변수인 1차 측 권선 수와 코어 재질선정을 FEM(Finite Elements Method) 해석을 통해 확인하였다.

• Structural Engineering and Mechanics
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• 제85권2호
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• pp.233-246
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• 2023

Bending and buckling analysis of multi-directional porous functionally graded sandwich plate has been performed for two cases namely: FG skin with homogeneous core and FG core with homogeneous skin. The principle of virtual displacements was employed and the solution was obtained using Navier's technique. This theory imposes traction-free boundary conditions on the surfaces and does not require shear correction factors. The validation of the present study has been performed with those available in the literature. The composition of metal-ceramic-based FGM changes in longitudinal and transverse directions according to the power law. Different porosity laws, such as uniform distribution, unevenly and logarithmically uneven distributions were used to mimic the imperfections in the functionally graded material that were introduced during the fabrication process. Several sandwich plates schemes were studied based on the plate's symmetry and the thickness of each layer. The effects of grading parameters and porosity laws on the bending and buckling of sandwich plates were examined.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1789-1803
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• 2022

RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo code MCS and a multi-group nodal diffusion solver. To demonstrate the feasibility of using MCS/RAST-F for fast reactor analysis, this paper presents the coupled nodal code verification results for the MET-1000 and CAR-3600 benchmark cores. Three different multi-group cross-section calculation schemes are employed to improve the agreement between the nodal and reference solutions. The reference solution is obtained by the MCS code using continuous-energy nuclear data. Additionally, the MCS/RAST-F nodal solution is verified with results based on cross-section generated by collision probability code TULIP. A good agreement between MCS/RAST-F and reference solution is observed with less than 120 pcm discrepancy in k_eff and less than 1.2% root-mean-square error in power distribution. This study confirms the two-step approach MCS/RAST-F as a reliable tool for the three-dimensional simulation of reactor cores with fast spectrum.

• Human Ecology Research
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• 제62권1호
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• pp.1-13
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• 2024

This study analyzed the current operational status, business continuity, and business continuity strategies of 11 Soho fashion shopping malls through a longitudinal case study (2019/2020 and 2022/2023). The aim was to determine how Soho fashion shopping malls are continuing their business having been successfully established in the fiercely competitive current online fashion market. Regarding changes in shopping mall operation status, all cases displayed changes in items, distribution channels, marketing channels, core values, and profit structures. After establishing the businesses, a crisis arose due to the COVID-19 pandemic, leading to difficulties in creating new customers. Moreover, there was excessive business expansion, resulting in saturation of the online platform store market. This meant companies were experiencing reduced sales (5) or difficulties in maintaining their business (3). However, there were differences in the direction of overcoming the crisis and continuing or converting the business. These revealed that to continue the business after successful establishment of an online fashion shopping mall, it is essential to have the expertise of entrepreneurs, work performance, and marketing ability, as well as differentiation capabilities such as product power and management strategy and core competitiveness that provides a relative advantage over other shopping malls. Customized government support at the level of the start-up ecosystem is also essential for the survival and business continuity of a SOHO online fashion shopping mall with poor human and material resources.

• Nuclear Engineering and Technology
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• 제41권8호
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• pp.1053-1064
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• 2009

The existence of a large sodium pool in the KALIMER, a pool-type LMR developed by the Korea Atomic Energy Research Institute, plays an important role in reactor safety and operability because it determines the grace time for operators to cope with an abnormal event and to terminate a transient before reactor enters into an accident condition. A two-dimensional hot pool model has been developed and implemented in the SSC-K code, and has been successfully applied for the assessment of safety issues in the conceptual design of KALIMER and for the analysis of anticipated system transients. The other important models of the SSC-K code include a three-dimensional core thermal-hydraulic model, a reactivity model, a passive decay heat removal system model, and an intermediate heat transport system and steam generation system model. The capability of the developed two-dimensional hot pool model was evaluated with a comparison of the temperature distribution calculated with the CFX code. The predicted hot pool coolant temperature distributions obtained with the two-dimensional hot pool model agreed well with those predicted with the CFX code. Variations in the temperature distribution of the hot pool affect the reactivity feedback due to an expansion of the control rod drive line (CRDL) immersed in the pool. The existing CRDL reactivity model of the SSC-K code has been modified based on the detailed hot pool temperature distribution obtained with the two-dimensional pool model. An analysis of an unprotected transient over power with the modified reactivity model showed an improved negative reactivity feedback effect.

• 한국정보통신학회논문지
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• 제23권12호
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• pp.1618-1623
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• 2019

본 논문에서는 광대역 전력선통신을 실현할 수 있는 유도성 커플러를 Fe계 나노결정립 합금을 이용하여 제작하고 성능을 분석하였다. 배전자동화시스템의 주상 및 지상개폐기에 적용하여 현장시험을 수행한 결과, 광대역 전력선통신의 주요 주파수대역에서 제작된 커플러는 분기 유무에 따라 통신속도의 차이는 있으나 비교적 우수한 데이터통신을 달성하는 것으로 측정되었다. 또한, 배전선로에서 발생되는 대전류 환경에서도 통신거리에 따라 전송률의 차이는 있으나 실시간 데이터 전송이 가능한 통신속도를 유지하는 것으로 확인되었다. 따라서 제작된 유도성 커플러는 접근성이 낮은 지역에 위치한 배전자동화시스템의 배전설비 상시 감시 및 원격제어에 활용함으로써 지능형 전력망 실현을 위한 핵심소자로 사용할 수 있을 것으로 판단된다.