본문 바로 가기

로고

국내 최대 기계 및 로봇 연구정보
통합검색 화살표
  • 시편절단기 Mecatome T260
  • 국내학술지

    29 0
    국내학술지 제목 게시판 내용
    제목(국문) 원자력 계통 열수력 해석코드의 부수로 유동혼합 모델 개발
    제목(영문)
    저자 김동위 (Dong Wi Kim ,부산대학교 기계공학부 석사과정 ) ▷공저자네트워크등록하기
    정재준 (J.J. leong ,부산대학교 기계공학부 ) ▷공저자네트워크등록하기
    초록
    초록(영문)

    Subchannel flow mixing is mportant for the accurate prediction of temperature and void fraction
    distributions in a nuclear reactor core. Dedicated subchannel analysis codes have been used for subchannel
    flow analysis by adopting either the so-called equal mass exchange (EM) or the equal-volume exchange and
    void drift (EVVD) model. The former is known to be good for a single-phase flow and, meanwhile, the
    latter is appropriate for both single- and two-phase flows. The nuclear thermal-hydraulic system code, SP ACE
    code, has been developed for the design and safety analysis of a pressurized water reactor. To extend its
    applicability to subchannel analysis, the state-of-the art EVVD model has been implemented into the SP ACE
    code in this work. The modified SP ACE code with the EVVD model was evaluated using the measured data
    from two-phase flow rod bundle tests (GE 9-rod test, ISPRA 16-rod test and PSBT 25-rod test). Based on
    the results, a new void drift coefficient KVD was suggested, which is an important parameter of the EVVD model.

    keyword SPACE Code, Subchannel Flow Mixing Model, EVVD Model, Two-phase Flow Analysis
    저널명 대한기계학회논문집 B ▷관련저널보기
    VOL 42
    PAGE 0665
    발표년도 2018
    국문File 국문다운로드
    영문File
    • 페이스북아이콘
    • 트위터 아이콘

    서브 사이드

    서브 우측상단1