• 에너지공학
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• 제20권3호
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• pp.178-184
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• 2011

압축공기저장(CAES) 발전은 가스터빈에 필요한 압축공기를 야간이나 비첨두 시간에 저렴한 전기로 미리 압축해서 저장하였다가 주간에 활용하는 것으로 전력 저장과 발전의 하이브리드 기술이라고 할 수 있다. 그러나 기존 압축공기저장 발전의 경우 심야에 압축공기를 일정부피의 압축공기 저장조에 충전하게 되면 저장조내의 압력은 점점 증가하게 되고, 반대로 주간에 발전을 위해 압축공기를 방출하게 되면 저장조내의 압력은 감소하게 된다. 이와 같이 운전 압력비 조건이 넓은 범위로 변화하여 설계 압력비에서 벗어나게 되는 것은 압축 및 팽창효율이 크게 감소하게 되는 원인이 된다. 본 논문에서는 이러한 기존의 변압식 압축공기저장 발전 방식의 문제점을 해결하기 위해 새로운 방식의 정압식 압축공기저장 발전 방식을 제시하고 있으며, 엑서지 개념을 포함한 에너지 분석을 통해 에너지 밀도 증가와 효율 향상 효과를 예측하였다. 새로운 방식의 정압식 압축공기 저장 발전 방식은 정압식 압축공기 저장 발전과 공압식 양수발전의 하이브리드 개념으로 기존 변압식 압축공기저장 발전 방식에 비해 정압 운전에 의한 효율향상과 에너지 밀도 증가로 압축공기 저장조의 크기를 50%이상 줄일 수 있는 장점을 가지고 있다.

• Computers and Concrete
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• 제14권2호
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• pp.127-143
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• 2014

LOCA (Loss Of Coolant Accident) is one of the most important utmost accidents for Prestressed Concrete Containment Vessel (PCCV) due to its coupled effect of high temperature and inner pressure. In this paper, heat conduction analysis is used to obtain the LOCA temperature distribution of PCCV. Then the elastic internal force of PCCV under LOCA temperature is analyzed by using both simplified theoretical method and FEM (finite element methods) method. Considering the coupled effect of LOCA temperature, a nonlinear elasto-plasitic analysis is conducted for PCCV under utmost internal pressure considering three failure criteria. Results show that the LOCA temperature distribution is strongly nonlinear along the shell thickness at the early time; the moment result of simplified analysis is well coincident with the one of numerical analysis at weak constraint area; while in the strong constrained area, the value of moments and membrane forces fluctuate dramatically; the simplified and numerical analysis both show that the maximum moment occurs at 6hrs after LOCA.; the strain of PCCV under LOCA temperature is larger than the one of no temperature under elasto-plastic analysis; the LOCA temperature of 6hrs has the greatest influence on the ultimate bearing capacity with 8.43% decrease for failure criteria 1 and 2.65% decrease for failure criteria 3.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.93-100
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• 2016

Since the sodium-cooled fast reactor is operated in a hostile environment due to the use of liquid sodium as its coolant, advanced techniques for in-service inspection are required to periodically verify the integrity of the reactor. This paper presents the development of in-service inspection techniques for Proto-type Generation IV Sodium-cooled Fast Reactor. First, the 10 m long plate-type ultrasonic waveguide sensor has been developed for in-service inspection of reactor internals, and its feasibility was verified through several under-water and under-sodium experiments. Second, the combined inspection system for in-service inspection of ferromagnetic steam generator tubes has been developed. The remote field eddy current testing and magnetic flux leakage testing can be conducted simultaneously by using the developed inspection system, and the detectability was demonstrated through several damage detection experiments. Finally, the electro-magnetic acoustic transducer which can withstand high temperature and be installable in the remote operated vehicle has been developed for in-service inspection of the reactor vessel, and its detectability was investigated through damage detection experiments.

• 대한기계학회논문집A
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• 제25권7호
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• pp.1139-1146
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• 2001

The reactor pressure vessel(RPV) is usually cladded with stainless steel to prevent corrosion and radiation embrittlement, and a number of subclad cracks have been found during an in-service-inspection. These subclad cracks should be assured for a safe operation under normal conditions and faulted conditions such as pressurized thermal shock(PTS). Currently available integrity assessment procedure for an RPV, ASME Code Sec. XI, are built on the basis of linear fracture mechanics (LEFM). In PTS condition, however, thermal stress and mechanical stress give rise to high tensile stress at the cladding and elastic-plastic behavior is expected in this area. Therfore, ASME Code Sec. XI is overly conservative in assessing the structural integrity under PTS condition. In this paper, the fracture parameter (stress intensity factor, K, and RT(sub)NDT) from elastic analysis using ASME Sec. XI and finite element method were validated against 3-D elastic-plastic finite element analyses. The difference between elastic and elastic-plastic analysis became significant with increasing crack depth. Therfore, it is recommended to perform elastic-plastic analysis for the accurate assessment of subclad cracks under TPS which causes plastic deformation at the cladding.

• 한국추진공학회지
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• 제17권5호
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• pp.80-85
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• 2013

본 논문은 평균값과 Allowable 값 기준의 구조 안전율과 구조 신뢰도와 관계 비교를 통해 복합재 추진기관의 확률적 구조 설계 방법을 설명하였다. 일반적으로 복합재 압력용기의 평균 값 기준의 구조설계는 1.5 이상의 구조 안전율과 0.999 이상의 구조 신뢰도 값이 요구된다. 요구 압력 기준의 0.999의 구조 신뢰도를 만족하기 위해서 평균 값 기준의 구조설계는 섬유 강도의 변동률에 따라 다른 구조 안전율을 부여해야한다. 그러나 이미 섬유 강도 변동률이 고려된 Allowable 값을 이용할 때는 고정된 안전율이 부여된다. 이상의 해석 결과로 볼 때 섬유 강도는 복합재 압력용기 구조 설계에 가장 중요한 설계 변수이고, 우수한 성능의 복합재 추진기관을 개발하기 위해서는 섬유 강도의 변동률이 최소화되어야 함을 알 수 있었다.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2007년도 동계학술발표대회 논문집
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• pp.310-315
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• 2007

The FTL has been developed to be able to irradiate test fuels at the irradiation hole(IR1 hole) by considering its utility and user's irradiation requirements. FTL consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). Test condition in IPS such as pressure, temperature and the water quality, can be controlled by OPS. For safety assurance IPS is designed to have dual stainless steel pressure vessel and OPS is composed of main cooling water system, emergency cooling water system, LMP(letdown, make-up, purification) system, etc. FTL Conceptual design was set up in 2001, basic design had completed including a design requirement, basic piping & instrument diagram (P&ID), and the detail design in 2004. In 2005, the development team carried out purchase and manufacture hardware and make a contract for construction work. FTL construction work began on August, 2006 and ended on March, 2007. After FTL development which is expected to be finished by 2008, FTL will be used for the irradiation test of the new PWR-type fuel and can maximize the usage of HANARO.

• 대한금속재료학회지
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• 제47권9호
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• pp.533-541
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• 2009

Materials used for a reactor pressure vessel(RPV) are required high strength and toughness, which determine the safety margin and life of a reactor. Ni-Mo-Cr low alloy steel shows better mechanical properties than existing RPV steels due to higher Ni and Cr contents compared to the existing RPV steels. The present study focuses on effects of Ni, Cr contents on the cleavage fracture toughness of Ni-Mo-Cr low alloy steels in the transition temperature region. The fracture toughness was characterized by a 3-point bend test of precracked Charpy V-notch(PCVN) specimens based on ASTM E1921-08. The test results indicated that the fracture toughness was considerably improved with an increase of Ni and Cr contents. Especially, control of Cr content was more effective in improving fracture toughness than manipulating Ni content, though Charpy impact toughness was changed more extensively by adjusting Ni content. These differences between changes in the fracture toughness and that in the impact toughness were derived from microstructural features, such as martensite lath size and carbide precipitation behavior.

• 대한금속재료학회지
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• 제46권12호
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• pp.771-779
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• 2008

An effective way of increasing the strength and fracture toughness of reactor pressure vessel steels is to change the material specification from that of Mn-Mo-Ni low alloy steel(SA508 Gr.3) to Ni-Mo-Cr low alloy steel(SA508 Gr.4N). In this study, we evaluate the effects of alloying elements on the microstructural characteristics of Ni-Mo-Cr low alloy steel. The changes in the stable phase of the SA508 Gr.4N low alloy steel with alloying elements were evaluated by means of a thermodynamic calculation conducted with the software ThermoCalc. The changes were then compared with the observed microstructural results. The calculation of Ni-Mo-Cr low alloy steels confirms that the ferrite formation temperature decreases as the Ni content increases because of the austenite stabilization effect. Consequently, in the microscopic observation, the lath martensitic structure becomes finer as the Ni content increases. However, Ni does not affect the carbide phases such as $M_{23}C_6 $ and $M_7C_3$. When the Cr content decreases, the carbide phases become unstable and carbide coarsening can be observed. With an increase in the Mo content, the $M_2C$ phase becomes stable instead of the $M_7C_3$ phase. This behavior is also observed in TEM. From the calculation results and the observation results of the microstructure, the thermodynamic calculation can be used to predict the precipitation behavior.

• 한국가스학회지
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• 제7권2호
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• pp.48-53
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• 2003

에너지 관련 플랜트에 사용되는 배관은 플랜트의 성능이나 안전성유지에 있어서 중요한 설비의 일부이다. 본 연구에서는 고압탄소강 배관의 변형 및 파괴에 대한 음향방출 기초 자료를 얻기 위하여 압력용기용 배관재를 기계가공하여 인장시험편을 만든 후, 인장시험을 실시하여 항복, 소성변형 및 파괴에 이르기까지의 음향방출 신호를 분석하였다. 탄성영역, 최대인장강도 이전의 소성영역 및 최대인장강도 이후의 소성영역에서 검출된 음향방출의 시간-주파수 분석 결과는 탄성영역에서 항복영역까지는 비교적 낮은 저주파수 대역(250${\~}$350kHz)이 나타났으며, 소성영역에서는 저주파수뿐만 아니라 고주파수 대역(500kHz)도 나타났다. 인장시험 후, 이러한 각 영역의 구별이 가능하였던 원인은 항복영역에서의 전위의 이동, 집적에 따른 신호와 최대인장강도 이전의 소성영역에서의 전위들이 개재물이나 결정입계를 통과했을 때 나타나는 신호, 최대인장강도 이후에는 미소공동의 발생, 성장 및 합체에 의하여 나타나는 신호로 분류가 가능하였기 때문인 것으로 판단된다.

• 대한조선학회논문집
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• 제52권6호
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• pp.485-493
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• 2015

Planing hull form is widely used as a high speed vessel hull. There is a problem of the planing hull not solved yet. The problem is that the planing hull has very large vertical acceleration and large heave and pitch motions. As one method for overcoming this problem, there is "wave-piercing hull". Before the motion in waves is investigated, the resistance and running attitude must be investigated. In this paper, the running attitude and resistance of two wave-piercing hulls are investigated by model tests. Model test results show that the wave-piercing hulls have large trim angle and sinkage at the high speed, so additional model tests are conducted by using the hull appended by stern interceptor that is very thin plate to increase the hydrodynamic pressure at the attached location. The results are compared with other planing hulls and the resistance components and the hydrodynamic force are discussed. From the model test results, it can be known that the stern interceptor is the effective appendage for the reduction of the resistance and trim angle of wave-piercing hull.