• 제목/요약/키워드: Full core

검색결과 493건 처리시간 0.035초

Design of Integrated Magnetic Transformer for ZVS Phase Shift Full Bridge Converter

  • Li, Xin-Lan;Jang, Eun-Sung;Shin, Yong-Whan;Won, Jae-Sun;Kim, Jong-Sun;Oh, Dong-Seong;Shin, Hwi-Beom
    • 전력전자학회:학술대회논문집
    • /
    • 전력전자학회 2008년도 하계학술대회 논문집
    • /
    • pp.40-42
    • /
    • 2008
  • This integrated magnetic (IM) transformer is proposed for a phase shifted full bridge (PSFB) converter with zero voltage switching (ZVS). In a new IM transformer, the transformer is located on the center leg of E-core and the output inductor is wound on two outer legs. The proposed circuit is analyzed electrically and magnetically. An E-core is redesigned and implemented. The proposed IM transformer is experimentally compared with the conventional one through a 1.2kW prototype converter.

  • PDF

SOC 테스팅을 위한 효율적인 부분 분리 링 (An Efficient Partial Isolation Ring Technique for SOC Testing)

  • 김문준;이영균;김석윤;장훈
    • 한국정보과학회논문지:시스템및이론
    • /
    • 제28권10호
    • /
    • pp.541-547
    • /
    • 2001
  • 코이를 기초로 설계된 칩을 테스팅 하기 위해서는 각 코어로의 테스트 데이터 접근을 위해 완전히 분리 링 필요하다. 부분 분리 링은 코어를 둘러싸고 있는 분리 링의 크기를 줄이고 분리 링으로써의 역할을 모두 수행한다. 본 논문에서는 기존의 방법들보다 부분 분리 링의 크기를 더욱 작게 하고 해법을 찾는 데 걸리는 시간보다 줄일수 있는 효율적인 방법을 제시한다. 이를 위해 테스트 가능도에 기반을 둔 효율적인 순위 결정 기법을 적용하였으며 SOC 테스팅의 특성을 살린 정렬 기법을 적용하였다. 실험결과에서 기존의 방법들보다 본 논문에 제시된 방법이 실제로 유용하다는 것을 보여준다.

  • PDF

Reactor core analysis through the SP3-ACMFD approach. Part I: Static solution

  • Mirzaee, Morteza Khosravi;Zolfaghari, A.;Minuchehr, A.
    • Nuclear Engineering and Technology
    • /
    • 제52권2호
    • /
    • pp.223-229
    • /
    • 2020
  • The present work proposes a solution to the static Boltzmann transport equation approximated by the simplified P3 (SP3) on angular, and the analytic coarse mesh finite difference (ACMFD) for spatial variables. Multi-group SP3-ACMFD equations in 3D rectangular geometry are solved using the GMRES solution technique. As the core time dependent analysis necessitates the solution of an eigenvalue problem for an initial condition, this work is hence devoted to development and verification of the proposed static SP3-ACMFD solver. A 3D multi-group static diffusion solver is also developed as a byproduct of this work to assess the improvement achieved using the SP3 technique. Static results are then compared against transport benchmarks to assess the proximity of SP3-ACMFD solutions to their full transport peers. Results prove that the approach can be considered as an acceptable interim approximation with outputs superior to the diffusion method, close to the transport results, and with the computational costs less than the full transport approach. The work would be further generalized to time dependent solutions in Part II.

한국 다국적기업의 해외진출에 대한 지분선택 : 현지합작 대비 단독투자 (The Choice between Shared vs. Full Ownership : The Case of Korean Multinational Corporations)

  • 박영규;박영렬
    • 무역상무연구
    • /
    • 제24권
    • /
    • pp.107-125
    • /
    • 2004
  • This study is based on the survey data of 74 Korean multinational corporations, which undertook foreign direct investments from 1980 to 1996. The study examined the firm-specific as well as the host country-specific factors affecting the decision between shared and full ownership. According to the results of this study, as for the firm-specific factors, Korean firms entering foreign markets in order to penetrate local markets prefer shared ownership while those pursuing core business diversification prefer full ownership. As for the host country factors, the more advanced the host country(such as OECD countries) is, the more preference is given to full ownership.

  • PDF

리스크정보 최적화를 통한 국내 연구용원자로의 안전성 향상 (Risk-Informed Optimization of Operation and Procedures for Korea Research Reactor)

  • 이윤환;장승철
    • 한국안전학회지
    • /
    • 제37권2호
    • /
    • pp.43-53
    • /
    • 2022
  • This paper describes an attempt to improve and optimize the operational safety level of a domestic research reactor by conducting a probabilistic safety assessment (PSA) under full-power operating conditions. The PSA was undertaken to assess the level of safety at an operating research reactor in Korea, to evaluate whether it is probabilistically safe and reliable to operate, and to obtain insights regarding the requisite procedural and design improvements for achieving safer operation. The technical objectives were to use the PSA to identify the accident sequences leading to core damage, and to conduct sensitivity analyses based thereon to derive insights regarding potential design and procedural improvements. Based on the dominant accident sequences identified by the PSA, eight types of sensitivity analysis were performed, and relevant insights for achieving safer operation were derived. When these insights were applied to the reactor design and operating procedure, the risk was found to be reduced by approximately ten times, and the safety was significantly improved. The results demonstrate that the PSA methodology is very effective for improving reactor safety in the full-power operating phase. In particular, it is a highly suitable approach for identifying the deficiencies of a reactor operating at full power, and for improving the reactor safety by overcoming those deficiencies.

매입형 합성보의 휨 성능 평가 -속 빈 프리캐스트 콘크리트 슬래브와 비대칭 H형강 철골보- (Flexural Capacity of Encased Composite Beam with Hollow Core PC Slabs)

  • 허병욱;배규웅;문태섭
    • 한국강구조학회 논문집
    • /
    • 제16권5호통권72호
    • /
    • pp.587-598
    • /
    • 2004
  • 본 연구에서는 합성보의 전체 춤을 절감할 수 있도록 속 빈 프리캐스트 콘크리트 슬래브를 철골보의 춤내에 삽입하여 일체화함으로써 철골조 고층건물에서 층고를 최소화 할 수 있는 이른바 "슬림플로어"공법에 대한 연구를 수행하였다. 본 연구는 콘크리트에 매입된 비대칭 철골보를 가지는 불완전 합성 슬림플로어 시스템의 휨 거동에 관한 것이다. 총 10개의 실대형 실험체를 철골보 춤, 속빈 프리캐스트 콘크리트 슬래브 춤, 슬래브 유효폭, 및 콘크리트 슬래브의 지지방식 별로 제작하여 실험을 수행하였다. 실험결과, 매입형 합성보의 경우, 별도의 전단연결재를 설치하지 않아도 자체가 가지고 있는 기계적 화학적 부착응력으로 인해 완전합성보에 비해서 0.48~0.98의 전단합성비를 나타내었다.

Full MOX Core Design for KNGR

  • Park, Yu-Seon;Kim, Yong-Hee;Lee, Kwang-Ho
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1999년도 추계학술발표회요약집
    • /
    • pp.59.2-59
    • /
    • 1999
  • PDF

Design of the flexible switching controller for small PWR core power control with the multi-model

  • Zeng, Wenjie;Jiang, Qingfeng;Du, Shangmian;Hui, Tianyu;Liu, Yinuo;Li, Sha
    • Nuclear Engineering and Technology
    • /
    • 제53권3호
    • /
    • pp.851-859
    • /
    • 2021
  • Small PWR can be used for power generation and heating. Considering that small PWR has the characteristics of flexible operating conditions and complex operating environment, the controller designed based on single power level is difficult to achieve the ideal control of small PWR in the whole range of core power range. To solve this problem, a flexible switching controller based on fuzzy controller and LQG/LTR controller is designed. Firstly, a core fuzzy multi-model suitable for full power range is established. Then, T-S fuzzy rules are designed to realize the flexible switching between fuzzy controller and LQG/LTR controller. Finally, based on the core power feedback principle, the core flexible switching control system of small PWR is established and simulated. The results show that the flexible switching controller can effectively control the core power of small PWR and the control effect has the advantages of both fuzzy controller and LQG/LTR controller.