• 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.

• 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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• 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.

• 대한조선학회논문집
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• 제55권5호
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• pp.371-378
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• 2018

Internal detonation of a warhead inside a compartment of naval vessel can result in serious blast damages including plastic deformation and rupture of the structural members especially bulkhead due to the huge explosive impact pressure, fragments and high temperature flame. To secure watertight integrity and to prevent the domino-type flooding of neighbouring compartments caused by the rupture of bulkheads, it is necessary to develop the structural design technology of Blast Hardened Bulkheads(BHB) which can resist the blast impact pressure of threatening weapons to increase the survivability of naval vessels. This study dealt with the simplified structural response analysis of BHB under impact pressure of confined explosion and aimed to develop the efficient and rational design method of BHB and joint structures which can be applied at initial design stage. The present 1st report dealt with the phenomena of explosive detonation surveying the preceding experimental/theoretical research and the characteristics of time history of blast pressure including the peak value and duration time were examined. And to predict the large plastic deformation behaviors of BHB by the huge blast pressure reasonably, the plastic hinge method including the membrane effects was formulated. It was applied to the simplified structural design equations. The following report will deal with the application and adjustment process of the structural scantling equations to the actual BHB design and verification of validity of them.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2005년도 추계학술대회 논문집
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• pp.555-559
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• 2005

Spinning process is a chipless metal forming method for axis-symmetric parts, which is more economical, efficient and versatile method for producing parts than other sheet metal forming process such as stamping or deep drawing. The large-sized spindle for spinning machine is the equipment to ferm a high-pressure vessel into the demanded shape. The important problem in the spindle system fur spinning machines is to reduce and minimize the thermal effect by motor and bearings. In this study, the effect of heat generation of bearings for the large-sized spindle is considered. Temperature distribution and thermal displacement of the spindle system for spinning machine can be analyzed by using the finite element method. The numerical results are compared with the measured data. The results show that temperature distribution and thermal displacement can be reasonably estimated by using the finite element method and the three dimensional model.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2477-2487
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• 2021

To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE. For a realistic simulation of a pressure and temperature (P/T) transient, the containment simulation vessel was designed to preserve a volumetric scale equivalently to the RCS volume scale of ATLAS. Three test cases for a steam line break (SLB) transient were conducted with variation of the initial condition of the passive heat sink or the steam flow direction. The test results indicated a stratified behavior of the steam-gas mixture in the containment following a high-temperature steam injection in prior to the spray injection. The test case with a reduced heat transfer on the passive heat sink showed a faster increase of the P/T inside the containment. The effect of the steam flow direction was also investigated with respect to a multi-dimensional distribution of the local heat transfer on the passive heat sink. The integral effect test data obtained in this study will contribute to validating the evaluation methodology for mass and energy (M/E) and P/T transient of the containment.

• Journal of Advanced Marine Engineering and Technology
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• 제39권4호
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• pp.425-431
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• 2015

선박의 LNG(liquefied natural gas) 연료 공급 시스템에서 천연가스는 $50^{\circ}C$의 온도와 35MPa의 압력을 가진 가스 상태로 기화기에서 엔진으로 이송되므로, 이러한 열 하중을 고려한 구조 안전성 평가가 반드시 필요하다. 본 연구에서는 먼저 재료에 미치는 열의 영향을 분석하기 위하여 이중 배관의 재료인 슈퍼 듀플렉스 스테인리스강의 어닐링 시간을 고려한 일축 인장 실험을 수행하였다. 또한 구조 안전성 평가를 위해, 현재 널리 사용되는 고정식 지지대를 가지는 고온-고압 이중 배관에 대한 열-구조 해석을 수행하였다. 지지대와 내관 사이의 응력 집중을 최소화하기 위하여, 내관을 따라 미끄러질 수 있는 슬라이딩 지지대의 새 형상들을 제안하였고, 열-구조 해석 결과를 통해 최적의 지지대를 제안하였다. 마지막으로 제안된 지지대를 사용한 전체 이중배관에 대한 해석을 통해 안전성을 평가하였다. 본 연구의 결과는 차후 LNG 연료 공급 시스템의 고온-고압 이중 배관 설계 시 참고자료로서 활용될 수 있으며, 이중 배관의 슬라이딩 지지대를 설계함에 있어서 그 활용가치가 있다고 판단된다.

• 한국가스학회지
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• 제15권4호
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• pp.7-14
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• 2011

20 L 구형 폭발시험장치와 시차주사열량계(DSC)를 사용하여 반응성 유기물 분진의 폭발 및 열분해 특성을 실험적으로 조사하였다. 그 결과 97 % Benzoyl peroxide(BPO), Phthalic anhydride(PA), 1-Hydroxybenzotri azol(HBT)의 폭발하한은 매우 낮은 농도인 10~15 g/$m^3$의 범위로 측정되어 착화위험성이 높은 것으로 나타났다. HBT, PA 및 97 % BPO의 폭발지수는 각각 251, 146, 80 [bar m/s]로서, HBT는 폭발등급 2에 해당한다. 또한 밀폐계 분진폭발의 화염전파 특성을 추정하기 위하여 용기면에의 화염도달시간과 폭발압력을 고려하여 화염전파속도를 예측하였다. 97 % BPO 및 HBT의 열분해 개시온도와 발열량은 각각 $107^{\circ}C$(1025 J/g), $214^{\circ}C$(1666 J/g)로 나타났는데, 이와같이 낮은 열분해 온도와 큰 발열량이 폭발특성에 영향을 주는 것으로 판단된다.

• Journal of Advanced Marine Engineering and Technology
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• 제38권7호
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• pp.868-876
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• 2014

본 논문에서는 함정에 탑재된 추진용 엔진에 사용되는 디젤연료(MDO)의 분사상태를 가시화가 가능한 단기통 디젤엔진에 적용시켜 전 후 분사시기에 따른 연소특성, 일산화탄소(CO) 및 탄화수소(HC) 배출특성을 규명하고, 연소과정의 가시화를 통하여 연소특성을 분석하는데 초점을 두었다. 전 분사시기가 주 분사시기 쪽으로 지연될수록 실린더 내부 평균유효압력($P_{me}$) 및 최고압력($P_m$)은 상승했으나, 주 분사의 방열율은 저감되고, 일산화탄소 및 탄화수소의 발생량 또한 감소하였다. 후 분사시기가 빨라질 경우 주 분사에 의해 형성된 고온, 고압 하에서 연소가 이루어짐에 따라 실린더 내부 평균유효압력 및 최고압력은 증가하였고, 일산화탄소 및 탄화수소 배출수준 또한 증가하였다. 연소과정을 분석한 결과, 전 분사시기가 늦어질수록 주 분사 시 발생되는 착화지연은 매우 짧아지며, 화염강도는 매우 상승하였다. 분사시기에 관계없이 후 분사 시 착화지연 현상은 발생하지 않았으며, 후 분사시기가 늦어질수록 화염의 강도는 점점 떨어졌다.

• 대한금속재료학회지
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• 제47권3호
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• pp.139-146
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• 2009

The heat-affected zone (HAZ) of SA508 Gr.4N Ni-Mo-Cr low alloy steel, which has higher Ni and Cr contents than SA508 Gr.3 Mn-Mo-Ni low alloy steel, was investigated on the microstructure and mechanical properties. The HAZ was categorized into seven characteristic zones (CGCG, FGCG, ICCG, SCCG, FGFG, ICIC and SCSC-HAZ) according to the peak temperature from the thermal cycle experienced during multi-pass welding. Post Weld Heat Treatment (PWHT) was conducted in the temperature range of $550{\sim}610^{\circ}C$ for 30 hours to evaluate the effect of PWHT conditions on the microstructure and mechanical properties. Before PWHT, CGHAZ and FGFGHAZ showed high yield strength (YS) ranging from 1000 to 1250 MPa, while YS of SCSCHAZ decreased from 607 MPa (observed for base metal) to 501 MPa. The Charpy impact energies of sub-HAZs fell below 100J at $-29^{\circ}C$, except in the SCSCHAZ. By applying PWHT to sub-HAZ specimens, YS decreased as the PWHT temperature increased. In the case of CGHAZs and FGFGHAZ heat-treated at $610^{\circ}C$, YS dropped drastically to the range of 654~686 MPa. From the Charpy impact test, the upper-shelf energy (USE) increased to approximately 250J and Index temperature ($T_{68J}$) decreased below $-50^{\circ}C$. Specifically, in FGFG, ICIC and SCSC-HAZ, $T_{68J}$ was below -110, which was lower than the case of base metal.