• 제목/요약/키워드: outer core

검색결과 307건 처리시간 0.025초

Outer Shock Interaction with Progenitor Winds in Young Core-Collapse SNRs

  • 이재준
    • 천문학회보
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    • 제37권1호
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    • pp.72.1-72.1
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    • 2012
  • Studying the environments in which core-collapse supernovae (SNe) explode and evolve is essential to establish the nature of the mass loss and the explosion of the progenitor star. The spatial structure of the outer shock in young core-collapse SNR provides an excellent opportunity to study the nature of the medium into which the remnant has been expanding. I will review studies of the outer shocks in young Galactic SNRs using Chandra X-ray observations and discuss the nature of the winds and the progenitor stars.

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핵심 객체 추출에 기반한 비주거 시설의 화재불꽃 추출에 관한 기초 연구 (A Basic Study on the Fire Flame Extraction of Non-Residential Facilities Based on Core Object Extraction)

  • 박창민
    • 디지털산업정보학회논문지
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    • 제13권4호
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    • pp.71-79
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    • 2017
  • Recently, Fire watching and dangerous substances monitoring system has been being developed to enhance various fire related security. It is generally assumed that fire flame extraction plays a very important role on this monitoring system. In this study, we propose the fire flame extraction method of Non-Residential Facilities based on core object extraction in image. A core object is defined as a comparatively large object at center of the image. First of all, an input image and its decreased resolution image are segmented. Segmented regions are classified as the outer or the inner region. The outer region is adjacent to boundaries of the image and the rest is not. Then core object regions and core background regions are selected from the inner region and the outer region, respectively. Core object regions are the representative regions for the object and are selected by using the information about the region size and location. Each inner region is classified into foreground or background region by comparing its values of a color histogram intersection of the inner region against the core object region and the core background region. Finally, the extracted core object region is determined as fire flame object in the image. Through experiments, we find that to provide a basic measures can respond effectively and quickly to fire in non-residential facilities.

Stator Core with Slits in Transverse Flux Rotary Machine to Reduce Eddy Current Loss

  • Lee, Ji-Young;Koo, Dae-Hyun;Kang, Do-Hyun;Hong, Jung-Pyo
    • Journal of Magnetics
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    • 제17권1호
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    • pp.51-55
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    • 2012
  • This paper presents an eddy current loss analysis for a transverse flux rotary machine (TFRM) with laminated stator cores, which consist of inner and outer cores whose laminated directions are perpendicular to each other. Although the TFRM is laminated to reduce eddy current losses, it still exhibits rapidly increasing core losses as the frequency increases. To solve this problem, slits are introduced to the stator outer core. 3-dimensional finite element analysis (3D FEA) based on the T-${\Omega}$ formulation is used to solve the eddy-current problem for a various numbers of slits in the nonlinear lamination core. The effects of the slits are confirmed using experiment data and 3D FEA results.

A Strategy for Kori Unit 1 Pressure Vessel Fluence Reduction through a Modification of Outer Assembly Configuration Using Monte Carlo Analysis

  • Kim, Jae-Cheon;Kim, Jong-Kyung;Kim, Jong-Oh
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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    • pp.515-519
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    • 1997
  • The purpose of this study is to reduce the fast neutron fluence at the reactor pressure vessel(RPV) and to provide a basis for plant-life extension. In this study, different neutron absorbers were employed in the core outer assemblies of Kori Unit 1 Cycle 14. The modified assemblies were used to calculate fast neutron fluence at the RPV and to evaluate reduction of outer assembly power and total power in core. By comparison with the case of no suppression fixture, the fast neutron fluence of a case with two rows stainless steel around the assembly with natural uranium pins is decreased by 85.8%. It is noted that the modification of outer assembly is more efficient than the previous low leakage loading pattern (LLLP) applied to Kori Unit 1. Also, compared fast neutron fluence in Cycle 1 with Cycle 14, fast neutron fluence at the RPV between Cycle 1 and Cycle 14 is not significantly different. It is found that LLLP applied to the Kori Unit 1 has not contributed to fast neutron fluence reduction at the RPV.

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An experimental assessment of resistance reduction and wake modification of a KVLCC model by using outer-layer vertical blades

  • An, Nam Hyun;Ryu, Sang Hoon;Chun, Ho Hwan;Lee, Inwon
    • International Journal of Naval Architecture and Ocean Engineering
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    • 제6권1호
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    • pp.151-161
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    • 2014
  • In this study, an experimental investigation has been made of the applicability of outer-layer vertical blades to real ship model. After first devised by Hutchins and Choi (2003), the outer-layer vertical blades demonstrated its effectiveness in reducing total drag of flat plate (Park et al., 2011) with maximum drag reduction of 9.6%. With a view to assessing the effect in the flow around a ship, the arrays of outer-layer vertical blades have been installed onto the side bottom and flat bottom of a 300k KVLCC model. A series of towing tank test has been carried out to investigate resistance (CTM) reduction efficiency and improvement of stern wake distribution with varying geometric parameters of the blades array. The installation of vertical blades led to the CTM reduction of 2.15~2.76% near the service speed. The nominal wake fraction was affected marginally by the blades array and the axial velocity distribution tended to be more uniform by the blades array.

칼라 영상에서의 중심 객체 추출에 관한 연구 (A Study on Extraction of Central Objects in Color Images)

  • 김성영;박창민;권규복;김민환
    • 한국멀티미디어학회논문지
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    • 제5권6호
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    • pp.616-624
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    • 2002
  • 본 논문에서는 영상에 포함된 중심 객체를 추출하는 방법에 대해 제시한다. 중심 객체는 촬영의 중심이 되어 영상의 중앙 부분에 비교적 큰 면적을 차지하는 객체로 정의하는데 영상 내용에 대한 중요한 정보를 제공한다. 중심 객체 추출을 위해 우선 입력 영상에 대해 해상도를 줄여가며 영상 분할하고 분할된 결과에 대해 계층적 영역 병합을 수행함으로써 객체가 많은 수의 영역으로 세분화되어 영상 분할되는 것을 방지할 수 있도록 하였다. 분할된 각 영역은 영상의 경계와 접하는 경계 영역과 그 외의 비경계 영역으로 분류하였다. 비경계 영역은 중심 객체에 해당될 가능성이 있는 영역으로써, 이들 중에서 영상 중심 부근에서 가장 큰 크기를 차지하는 영역이 핵심객체영역으로 선택된다. 또한 경계 영역 중에서 영상의 네 모서리에 인접하는 영역은 핵심배경영역으로 선택되어 핵심객체영역과 함께 중심 객체 추출에 이용된다. 각 비경계 영역은 핵심 배경영역및 핵심객체영역과 칼라 분포 유사도출 비교하여 배경영역과 전경영역으로 분류된다. 핵심객체영역 및 핵심객체영역과 연결성을 가지는 전경영역이 최종 중심 객체로 선택된다. 본 논문에서 제안된 방법은 비교적 복잡한 배경을 갖는 영상에 대해서도 어느 정도 만족할 만한 결과를 얻을 수 있었다.

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Two-mode Fiber with a Reduced Mode Overlap for Uncoupled Mode-division Multiplexing in C+L Band

  • Hong, Seongjin;Choi, Kyoungyeon;Lee, Yong Soo;Oh, Kyunghwan
    • Current Optics and Photonics
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    • 제2권3호
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    • pp.233-240
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    • 2018
  • We proposed a two-mode fiber (TMF) design that can effectively reduce the mode overlap between $LP_{01}$ and $LP_{11}$ modes by using a W-shaped index profile core structure, which is a primary concern in uncoupled mode division multiplexing (MDM). TMF has a three-layered core structure; central circular core, inner cladding, and outer ring core. We confirmed that in an optimal structure the $LP_{01}$ mode was highly confined to the central core while the $LP_{11}$ mode was guided along the outer ring core to result in a minimum overlap integral. We used a full-vectorial finite element method to estimate effective index, differential group delay (DGD), confinement loss, chromatic dispersion, and mode overlap controlling the parameters of the W-shaped structure. The optimized W-profile fiber provided optical characteristics within the ITU-T recommended standards over the entire C+L band.

Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life

  • Ahmadi, M.;Pirouzmand, A.;Rabiee, A.
    • Nuclear Engineering and Technology
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    • 제50권7호
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    • pp.1037-1042
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    • 2018
  • The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the Safety Analysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outer irradiation sites with water. At the end of the MNSR core life, 10.95 cm of Beryllium is added to the top of the core as a reflector which affects some neutronic parameters such as effective delayed neutrons fraction (${\beta}_{eff}$), the reactivity worth of inner and outer irradiation sites that are filled with water and the reactivity worth of the control rod. Given those influences and changes, new neutronic calculations are required to be able to demonstrate the reactor safety. Therefore, a validated MCNPX model is used to calculate all neutronic parameters at the end of the reactor core life. The calculations show that the induced reactivity in the BDBA scenario increases at the end of core life to $7.90{\pm}0.01mk$ which is significantly higher than the induced reactivity of 6.80 mk given in the SAR of MNSR for the same scenario but at the beginning of the core's life. Also this value is 3.90 mk higher than the maximum allowable operational limit (i.e. 4.00 mk).

난류경계층에 의한 다층재질 원통형 실린더의 유체소음 해석 연구 (A Study of Flow Induced Noise for Multilayered Cylinder due to Turbulent Boundary Layer)

  • 신구균;홍진숙;이헌곤
    • 소음진동
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    • 제6권5호
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    • pp.671-677
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    • 1996
  • This paper presents the analytical method for predicting turbulence- induced noise in the multilayered cylinder composed of an outer hose, an inner fluid and an internal core. It is assumed that an infinite axisymmetric cylinder is located horizontally in water with free stream velocity and the turbulent boundary layer (TBL) surrounding the outer hose is fully developed and homogeneous. The transfer function at the core surface due to the propagation of the pressure fluctuation within the TBL is formulated using the linearized Navier-Stockes equation for solid and fluid. In the estimation of the energy spectrum of wall pressure fluctuation, the empirical formula proposed by Strawderman based on the Corcos model is used. A general algorithm for the calculation of the pressure level at the surface of a core, that is, turbulence- induced noise, is presented. Through the detailed numerical simulation, it is found that the major noise mechanism is the propagation of the bulge wave along hose.

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Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO

  • Noh, Tae-yang;Park, Byung-Gun;Kim, Myong-Seop
    • Nuclear Engineering and Technology
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    • 제50권3호
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    • pp.446-452
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    • 2018
  • To improve the accuracy and safety of irradiation tests in High flux Advanced Neutron Application ReactOr (HANARO), the nuclear energy deposition rate, which is called nuclear heating, was estimated for an irradiation capsule with an iridium sample in the irradiation hole in order. The gamma rays emitted from the radioisotopes (RIs) of the structural materials such as flow tubes of fuel assemblies and heavy water reflector tank were considered as radiation source. Using the ORIGEN2.1 code, emission rates of delayed gamma rays were calculated in consideration of the activation procedure for 8 years and 2 months of HANARO operation. Calculated emission rates were used as a source term of delayed gamma rays in the MCNP6 code. By using the MCNP code, the nuclear heating rates of the irradiation capsules in the inner core, outer core, and heavy water reflector tank were estimated. Calculated nuclear heating in the inner core, outer core, and heavy water reflector tank were 200-260 mW, 80-100 mW, and 10 mW, respectively.