• 제목/요약/키워드: Thermal Transport Conditions

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대형 레이더 기계구조부 개발 절차 (Development Process of Mechanical Structure for a Large Radar)

  • 신동준;이종학;강영식
    • 한국군사과학기술학회지
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    • 제20권1호
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    • pp.1-11
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    • 2017
  • In this paper, design requirements of the large radar were investigated, and development was performed through the analysis and design. Large radar should be designed by bearing the 75 knot wind force and $20kg/m^2$ ice mass as operating conditions in order to meet structural stability, and driving torque and bearing load were calculated for securing the driving stability. Thermal dissipation analysis was performed considering TRM and DC-DC Converter's limitation temperature by $50^{\circ}C$ ambient temperature condition in order to attain thermal stability, and PSD and shock analysis were carried out by using MIL-STD-810G vibration and shock specification in order to transport and installation of the large radar. As a result, all components of large radar could secure the structural stability more than 2.8 factor of safety, and driving stability was also secured with adequate bearing fatigue life. Thermal stability was attained by allowable max temperature 88.7 C of the TRM, and structural stability for transportation and installation of the large radar was also secured more than 5 factor of safety. After it was transported and installed to the radar site, operating capability was finally verified by rotating the large radar.

탄화수소 연료 액적의 연소 특성에 관한 수치해석 (A Numerical Study of Combustion Characteristics of Hydrocarbon Fuel Droplet)

  • 이봉수;이경재;김종현;구자예
    • 대한기계학회논문집B
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    • 제27권11호
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    • pp.1595-1603
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    • 2003
  • Droplet combustion at high ambient pressures is studied numerically by formulating one dimensional combustion model in the mixture of n-heptane fuel and air. The ambient pressure is supercritical conditions. The modified Soave-Redlich-Kwong state equation is used in the evaluation of thermophysical properties to account for the real gas effect on fluid p-v-T properties in high pressure conditions. Non-ideal thermodynamic and transport property at near critical and supercritical conditions are also considered. Several parametric studies are performed by changing ambient pressure and initial droplet diameter. Droplet lifetime decreased with increasing pressure. Surface temperature increased with increasing pressure. Ignition time increased with increasing initial droplet diameter. Temporal or spatial distribution of mass fraction, mass diffusivity, Lewis number, thermal conductivity, and specific heat were presented.

단순화된 피동 원자로건물 냉각계통 내 자연순환에 관한 수치적 연구 (Numerical Investigation on Natural Circulation in a Simplified Passive Containment Cooling System)

  • 서정수
    • 한국안전학회지
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    • 제33권3호
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    • pp.92-98
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    • 2018
  • The flow of cooling water in a passive containment cooling system (PCCS), used to remove heat released in design basis accidents from a concrete containment of light water nuclear power plant, was conducted in order to investigate the thermo-fluid equilibrium among many parallel tubes of PCCS. Numerical simulations of the subcooled boiling flow within a coolant loop of a PCCS, which will be installed in innovative pressurized-water reactor (PWR), were conducted using the commercially available computational fluid dynamics (CFD) software ANSYS-CFX. Shear stress transport (SST) and the RPI model were used for turbulence closure and subcooled flow boiling, respectively. As the first step, the simplified geometry of PCCS with 36 tubes was modeled in order to reduce computational resource. Even and uneven thermal loading conditions were applied at the outer walls of parallel tubes for the simulation of the coolant flow in the PCCS at the initial phase of accident. It was observed that the natural circulation maintained in single-phase for all even and uneven thermal loading cases. For uneven thermal loading cases, coolant velocity in each tube were increased according to the applied heat flux. However, the flows were mixed well in the header and natural circulation of the whole cooling loop was not affected by uneven thermal loading significantly.

Failure Analysis of Stress Reliever in Heat-Transport Pipe of District Heating System

  • Cho, Jeongmin;Chae, Hobyung;Kim, Heesan;Kim, Jung-Gu;Kim, Woo Cheol;Lee, Soo Yeol
    • Corrosion Science and Technology
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    • 제21권4호
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    • pp.243-249
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    • 2022
  • The objective of the present study was to perform failure analysis of double-layered bellow (expansion joint), a core part of stress reliever, used to relieve axial stresses induced by thermal expansion of heat-transport pipes in a district heating system. The bellow underwent tensile or compressive stresses due to its structure in terms of position. A leaked position sufferred a fatigue with a tensile component for decades. A cracked bellow contained a higher fraction of martensitic phase because of manufacturing and usage histories, which induced more brittleness on the component. Inclusions in the inner layer of the bellow acted as a site of stress concentration, from which cracks initiated and then propagated along the hoop direction from the inner surface of the inner layer under fatigue loading conditions. As the crack reached critical thickness, the crack propagated to the outer surface at a higher rate, resulting in leakage of the stress reliever.

Charge Transport Properties of Polyaniline-gold/graphite Oxide Composite Films

  • Basavaraja, C.;Kim, Won-Jung;Thinh, P.X.;Huh, Do-Sung
    • Bulletin of the Korean Chemical Society
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    • 제33권2호
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    • pp.449-452
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    • 2012
  • A polyaniline-gold composite was prepared via the polymerization of aniline hydrochloride with or without water-soluble graphite oxide using auric acid as an oxidant. The reaction products were characterized using Xray photoelectron spectroscopy. The thermal stability and embedded crystallinity of the composites were also investigated using thermogravimetric and X-ray diffraction analyses. The electrical properties of the composites were examined using cyclic voltammetric measurements at room temperature and temperature-dependent DC conductivity within 300-500 K. Compared to pure graphene oxide and polyaniline-gold composite, the polyaniline-gold-graphene composite exhibited higher crystallinity and thermal stability, and higher current density response under equivalent conditions.

투명 단열외피의 열적성능에 관한 연구 (Thermal Effect of the Transparent Insulated Opaque Envelopes)

  • 김세환;이성
    • 교육녹색환경연구
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    • 제4권4호
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    • pp.19-24
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    • 2004
  • The thermal effect of a transparent insulated opake wall with solar energy was investigated theoretically. The heat gain through transparent insulated opake wall was studied for relative simple conditions. The stationary heat transport effect was studied for layer which is built on the opake wall. This study shows that a relative low solar radiation intensity causes a great heat reduction through the transparent insulated opake wall. Because the transparent insulation layer is mostly transparent to solar radiation, it is opaque to heat radiation.

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학교건물의 에너지 절약에 관한 연구 - 투명 단열외피의 열적성능을 중심으로 - (Study on the Energy Saving for School Buildings - through thermal effect of the transparent insulated opaque envelopes -)

  • 이성;김세환;김기철
    • 동력기계공학회지
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    • 제10권1호
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    • pp.41-45
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    • 2006
  • The thermal effect of a transparent insulated opake wall with solar energy was investigated theoretically. The heat gain through transparent insulated opake wall was studied for relative simple conditions. The stationary heat transport effect was studied for layer which is built on the opake wall. This study shows that a relative low solar radiation intensity causes a great heat reduction through the transparent insulated opake wall.

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고품질 질화물 반도체 박막 성장을 위한 반응로 구조 및 열적 조건에 관한 연구 (A Study on the Reactor Configuration and Thermal Conditions for the Growth of High Quality Thin Film of GaN Layer)

  • 김진택;백병준;이철로;박복춘
    • 대한기계학회논문집B
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    • 제28권12호
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    • pp.1632-1639
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    • 2004
  • Numerical calculation has been performed to investigate the transport phenomena in the horizontal reactor which has two different gas inlets for MOCVD(metalorganic chemical vapor deposition). The full elliptic governing equations for continuity, momentum, energy and chemical species are solved by using the commercial code FLUENT. It is investigated how thermal characteristics, reactor geometry, and the operating parameters affect flow fields, mass fraction of each reactants. The numerical simulations demonstrate that flow rate of each species, inlet geometry of the reactor, and its distance from the susceptor as well as the inclination of upper wall of reactor can be used effectively to optimize reactor performance. The commonly used idealized boundary conditions are also investigated to predict flow phenomena in the actual deposition system.

B형 삼중수소 운반용기 안정성 평가 (Safety evaluation of type B transport container for tritium storage vessel)

  • 이민수;백승우;김광락;안도희;임성팔;정홍석;최희주;최종원;손순환;송규민
    • 방사성폐기물학회지
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    • 제5권2호
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    • pp.155-169
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    • 2007
  • 월성 원자력 발전소의 TRF 시설에서 수집된 트리튬을 metal hydride 형태로 보관하고 있는 500 kCi급 트리튬 1차 저장용기를 발전소 밖의 폐기물 저장고로 안전하게 운반하기 위하여 트리튬 운반용기를 개발하였다. B형 운반용기의 기술기준을 적용하여 구조평가, 열평가, 방사선차폐평가, 격납평가 등을 수행하여 운반용기의 안전성을 분석하였다. 트리튬 운반용기는 정상운반조건 및 사고운반조건에서도 격납 경계가 손상되지 않는다고 평가되었다. 붕괴열로 인한 운반용기 내부 저장용기의 온도상승은 수치해석 결과, 원통형 모델에서는 $134.8^{\circ}C$로 나타났다. 운반사고 조건에 대한 열 평가로서 $800^{\circ}C$ 외부환경에 30분간 노출되었을 경우에는 단열재만의 열차폐를 고려하여 계산한 결과, 약 $405^{\circ}C$로 나타났으며, 내부 온도 상승은 1차 격납 경계인 1차 저장용기의 허용 온도인 $550^{\circ}C$에도 미치지 못하였다. 격납 차폐 평가에서도 사고조건인 $800^{\circ}C$의 외부 환경에 노출된 경우에서도 충분히 운반용기의 격납 성능을 유지할 수 있다고 판단되었다. 방사선에 대한 차폐 특성을 조사한 결과, 트리튬에서 발생된 ${\beta}-ray$ 선량은 1차 저장용기 외부 표면에서 0으로 계산되었다. 이상과 같이 500 kCi 급 트리튬 운반용기에 대한 안전성을 평가한 결과, 운반사고조건에서도 트리튬 운반용기는 전혀 이상이 없는 것으로 나타났다.

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A Loss-of-RHR Event under the Various Plant Configurations in Low Power or Shutdown Conditions

  • Seul, Kwang-Won;Bang, Young-Seok;Lee, Sukho;Kim, Hho-Jung
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.551-556
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    • 1997
  • A present study addresses a loss-of-RHR event as an initiating event under specific low power or shutdown conditions. Two typical plant configurations, cold leg opening case with water-filled steam generators and pressurizer opening case with emptied steam generators, were evaluated using the RELAP5/ MOD3.2 code. The calculation was compared with the experiment conducted at ROSA-IV/LSTF in Japan. As a result, the code was capable of simulating the system transient behavior following the event. Especially, thermal hydraulic transport processes including non-condensable gas behavior were reasonably predicted with an appropriate time step and CPU time. However, there were some code deficiencies such as too large system mass errors and severe flow oscillations in core region.

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