• Nuclear Engineering and Technology
• /
• 제25권3호
• /
• pp.413-423
• /
• 1993

본 논문에서는 경수로 노심 용융사고시 1차계통의 압력이 높은 경우에 발생하는 격납용기 직접가열 현상에 대한 실험연구를 하였다. 실험은 고리 1,2호기와 영광 3,4호기의 1/30 축소규모와 고리 1,2호기의 1/20 축소규모를 실험모형으로 하여 수행되었으며, 고리 1,2호기의 경우 축소 규모에 따른 검증도 시도하였다. 실험의 주요 변수는 초기 압력 용기의 압력, 파열면적 및 캐비티의 구조 등이다. 실험결과로부터 캐비티 외부로의 용융노심 분사비율은 높은 초기압력과 큰 파열면적을 가진 경우가 더 높으며 캐 비티의 구조가 분사비율에 큰 영향을 미침을 알 수 있었다. 본 연구의 실험결과를 이용하여 분사비율에 대한 실험관계식을 무차원 유효시간의 함수로 도출하여 제시하였으며, 이 실험관계식은 본 실험결과 뿐만 아니라 한국 과학기술원의 실험자료 및 미국 BNL 실험결과와도 잘 일치하였다.

• Journal of Welding and Joining
• /
• 제34권5호
• /
• pp.47-53
• /
• 2016

The aim of this study is to consider effect of weld elastic modulus on simulations of stress concentration and fatigue life for pressure vessel. The investigations include analysis with ADINA and WINLIFE softwares for whole body model about using condition of the boiler vessel. Values of weld elastic modulus were divided by 5 steps in butt weld area of the boiler vessel body. The stress concentration of the butt weld more was increased in case of higher elastic modulus of weld area because of higher difference of material properties between matrix and weld. It was concluded that the fatigue lives were decreased along increasing stress concentration due to high elastic modulus of weld. The matrix microstructure was estimated as pearlitic structure of ${\alpha}$ ferrite and pearlite. And the microstructures of welds along 5 steps of elastic modulus were estimated as bainitic fine pearlite and martensite as increasing elastic modulus.

• 대한기계학회논문집A
• /
• 제34권7호
• /
• pp.947-952
• /
• 2010

압력용기, 유압호스 조립체, 어큐뮤레이터, 유압실린더, 유압밸브, 파이프 등의 제품들의 시험은 일반적으로 ISO와 SAE에서 정의되는 충격압력 조건들로 작동되고 있다. 충격압력 시험 장비는 높은 압력, 정확한 제어 시스템, 장기간 사용할 수 있는 수명을 가지는 것이 요구되며, 언급된 사항들은 유압 시스템에서 보다 높은 압력이 발생되어지는 충격압력 발생기를 제작하는데 필요하다. 충격압력 시험기는 제어는 편리하지만 높은 가격인 서보밸브 제어 시스템이 적용되었다. 제어 시스템의 적용은 시험하는 제품들에 영향을 주는 압력의 파형을 생성한다. 본 연구는 유량과 압력, 압력의 상승속도를 고려한 충격압력 발생시스템 설계 및 제작 과정을 연구하는 것을 목적으로 한다. 이것은 또한 결과로써 시스템에서 초고압의 압력을 발생시키는 압력 파형을 얻을 수 있었다.

• 한국전산유체공학회:학술대회논문집
• /
• 한국전산유체공학회 2009년 추계학술대회논문집
• /
• pp.121-128
• /
• 2009

During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by a following jet of a high-pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet and released into other compartments of the NPP by a overpressure in the cavity. The fragments of the corium transfer thermal energy to the ambient air in the containment or interact chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical process. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. In this study, MC3D code was used to evaluate the dispersion rates in the APR1400 NPP during the high-pressure accidents. MC3D is a two-phase analysis code based on Eulerian four-fields for melt jet, melt droplets, gas and water. The dispersion rates of the corium melt depending on the RPV pressure were obtained from the MC3D analyses and the values specific to the APR1400 cavity geometry were compared to a currently available correlation.

• 한국전산구조공학회논문집
• /
• 제30권3호
• /
• pp.207-214
• /
• 2017

국내의 72.5kV 이상, 주파수 60Hz의 송배전설비인 옥내 및 옥외용 가스절연개폐장치(GIS)는 내진 안전성에 대해 국가에서 정한 한전표준규격(ES-6110-0002)을 만족해야 한다. 이 규격에서 명시되지 않은 사항은 IEC 62271-203, 62271-207 등의 관련 기기 규격에 준한다. 한전표준규격에서 기기는 정상사용상태와 특수사용상태에서 건전성이 유지되어야 한다. 안전성 판단을 위해 ASME BPVC SEC.VIII 내압용기 설계 기준에 의해 A6061-T6 재질의 GIS에 대한 정상사용상태 기준과 국내 한전표준규격과 국외 IEC 62271-207에 의한 특수사용상태 기준(지진)에 대한 총체적 응력상태를 판단하였다. 한전표준규격 기준(0.22g) 적용시, 최종응력이 알루미늄인 Part A는 78.2MPa, Part D2의 경우 102.3MPa로, ASME 허용응력 값 181.5MPa를 만족하고 있다. IEC 62271-207 High 0.5g의 경우에도 최종응력은 Part A는 90.5MPa, Part D2는 103.8MPa이다. 본 연구 결과, 72.5kV GIS는 한전표준규격의 구조안전성과 내진성능을 충분히 만족함을 보이고 있다. 내진해석으로 내진시험을 수행할 수 없는 대형 전력기기의 내진성능 실증에 활용될 수 있을 것으로 기대된다.

• Nuclear Engineering and Technology
• /
• 제47권5호
• /
• pp.534-545
• /
• 2015

In the very high temperature reactor (VHTR), which is a next generation nuclear reactor system, ceramics are used as a fuel coating material and graphite is used as a core structural material. Even if a depressurization accident occurs and the reactor power goes up instantly, the temperature of the core will change only slowly. This is because the thermal capacity of the core is so high. Therefore, the VHTR system can passively remove the decay heat of the core by natural convection and radiation from the surface of the reactor pressure vessel. The objectives of this study are to investigate the heat transfer characteristics of natural convection of a one-side heated vertical channel with inserted porous materials of high porosity and also to develop the passive cooling system for the VHTR. An experiment was carried out using a one-side heated vertical rectangular channel. To obtain the heat transfer and fluid flow characteristics of the vertical channel with inserted porous material, we have also carried out a numerical analysis using a commercial Computational Fluid Dynamics (CFD) code. This paper describes the thermal performances of the one-side heated vertical rectangular channel with an inserted copper wire of high porosity.

• 수산해양기술연구
• /
• 제59권1호
• /
• pp.35-43
• /
• 2023

Sensory evaluation of shucking pressure, pressure holding time, seeding method, difference in full shucking rate in the aquaculture area and shucking oyster was performed using an ultra-high pressure oyster shucking machine. The reaching time for each target pressure is 2.2-2.4 MPa/sec in the range of 180 MPa to 240 MPa. had a rate of pressure rise. There was a difference of 0.5-1.7℃ in the range of 24-27℃ in the seawater temperature before and after the pressure treatment inside the pressure vessel, but there was no specific increase or decrease in seawater temperature. When only the shucking pressure is increased without the pressure holding time, the critical shucking pressure at which the oyster shell is opened and the flesh is peeled in the range of 200 to 220 MPa. When the critical shucking pressure is reached, the oyster sample in the closed vessel is expected to be shucked by about 40%. If there is no pressure holding time when judged only by full shucking, an increase in pressure of about 1.5 MPa is required to further shuck 3% of the oyster population. The oyster samples cultivated in the south coast of Korea were subject to full shucking under the conditions of 220 MPa shucking pressure and two minutes (120 seconds) of pressure holding time, and the difference in the pressure of the oysters according to the oyster seeding method and the farming area was minute. Finally, the condition of 220 MPa of shucking pressure and three minutes of pressure holding time was the best at 1.52 when the result of the sensory evaluation performed manually was set to 1.0. Next was 1.4 under the conditions of 220 MPa of shucking pressure and one minute of pressure holding time (60 seconds), and 1.3 under the condition of 220 MPa and two minutes of pressure holding time (120 seconds). Therefore, it is considered that the most desirable shucking conditions, considering the efficiency and sensory evaluation results, are the conditions of 220 MPa shucking pressure and two to three minutes of pressure holding time.

• 한국가스학회지
• /
• 제2권4호
• /
• pp.1-6
• /
• 1998

중화학 플랜트의 고온고압 요소인 증기 발생기(steam generator)의 드럼, 헤더 및 헤더 스터브 설계에 응력해석에서 부터 도면자동작도, 제작용 서류 자동생성에 이르기까지의 제반설계과정을 체계적으로 연결시킨 설계정보 통합 관리로 단순 설계오류를 줄이고, 또한 설계변경에 대해 신속한 재설계가 가능한 효율적인 설계를 도모하기 위하여 "피로수명을 고려한 헤더스터브 형상설계 모듈", "TRD301을 기초로한 후육내압부 운전조건(기동/정지 조건) 및 수명평가 모듈", "헤더 및 드럼부 자동작도 모듈"을 개발하였다. 이에 따라 형상설계 모듈을 이용하여 설계된 스터브 형상을 토대로 수명평가 모듈로 수명을 평가한 후 상세설계 도면 및 관련 서류의 자동작도로 이어지는 일관된 종합설계 시스템을 구축하였다.

• Journal of Mechanical Science and Technology
• /
• 제18권12호
• /
• pp.2310-2318
• /
• 2004

The effects of change in injection pressure on spray structure in high temperature and pressure field have been investigated. The analysis of liquid and vapor phases of injected fuel is important for emissions control of diesel engines. Therefore, this work examines the evaporating spray structure using a constant volume vessel. The injection pressure is selected as the experimental parameter, is changed from 400 bar to 800 bar by using a common rail injection system. Also, we conducted simulation study by modified KIVA-II code. The results of simulation study are compared with experimental results. The images of liquid and vapor phase for free spray were simultaneously taken by exciplex fluorescence method. As experimental results, the vapor concentration of injected fuel is leaner due to the increase of atomization in the case of the high injection pressure than in that of the low injection pressure. The calculated results obtained by modified KIVA-II code show good agreements with experimental results.

• 한국기계가공학회지
• /
• 제17권4호
• /
• pp.23-31
• /
• 2018

Stress of a steam separator, equipment of the high-pressure (HP) evaporator for a HRSG, was analyzed and evaluated according to ASME Boiler & Pressure Vessel Code Section VIII Division 2. First, from the analysis results of the piping system model of the HP evaporator, reaction forces of the riser tubes connected to the steam separator, i.e., nozzle loads, were derived. Next, a finite element model of the steam separator was constructed and analyzed for the design pressure and the nozzle loads. The results show that the maximum stress occurred at the bore of the riser nozzle. The primary membrane stresses at the shell and nozzle were found to be less than the allowable stress. Next, the steam separator was analyzed for the steady-state operating conditions of operating pressure, operating temperature, and nozzle loads. The maximum stress occurred at the bore of the riser nozzle. The primary plus secondary membrane plus bending stress at the shell and nozzle was found to be less than the allowable stress.