RISS 학술연구정보서비스

검색

인기 검색어

    다국어 입력

    http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.

    변환된 중국어를 복사하여 사용하시면 됩니다.

    예시)
    • 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
    • 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
    닫기
    KCI등재

    CUPID 코드를 활용한 ROCOM 붕소 혼합 문제 해석 = Simulation of Boron Mixing Benchmark using the CUPID Code

    한글로보기

    https://www.riss.kr/link?id=A105975078

    • 0

      상세조회
    • 0

      다운로드
    서지정보 열기
    • 내보내기
    • 내책장담기
    • 공유하기
    • 오류접수

    부가정보

    다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

    The concentration of boron in the coolant of reactor cooling system in nuclear power plants(NPPs) plays an important role in controlling the reactivity according to fuel burn-up. Thus, an accurate prediction of the boron concentration after an unexpected de-borated water injection is required for the safety of NPPs. Korea Atomic Energy Research Institute(KAERI) participates in the ROCOM boron dilution benchmark in a framework of IAEA coordinated research projects. Through the benchmark, the capability of the CUPID code to predict the boron mixing behavior was validated. Two-equations RANS turbulence models were tested such as the standard k-ε model, RNG k-ε model, and SST k-ω model. The calculation results showed that the standard k-ε model reasonably predicted the boron mixing behavior when appropriate y+ values were verified even though the k-ε model required less number of cells comparing to the SST k-ω model because of larger y+ values.
    번역하기

    The concentration of boron in the coolant of reactor cooling system in nuclear power plants(NPPs) plays an important role in controlling the reactivity according to fuel burn-up. Thus, an accurate prediction of the boron concentration after an unexpec...

    The concentration of boron in the coolant of reactor cooling system in nuclear power plants(NPPs) plays an important role in controlling the reactivity according to fuel burn-up. Thus, an accurate prediction of the boron concentration after an unexpected de-borated water injection is required for the safety of NPPs. Korea Atomic Energy Research Institute(KAERI) participates in the ROCOM boron dilution benchmark in a framework of IAEA coordinated research projects. Through the benchmark, the capability of the CUPID code to predict the boron mixing behavior was validated. Two-equations RANS turbulence models were tested such as the standard k-ε model, RNG k-ε model, and SST k-ω model. The calculation results showed that the standard k-ε model reasonably predicted the boron mixing behavior when appropriate y+ values were verified even though the k-ε model required less number of cells comparing to the SST k-ω model because of larger y+ values.

    더보기

    참고문헌 (Reference)

    1 J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" 한국원자력학회 42 (42): 636-655, 2010

    2 "SALOME website"

    3 윤한영, "Recent Improvements in the CUPID Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components" 한국원자력학회 46 (46): 655-666, 2014

    4 OECD, "Proceedings of the OECD/NEA/CSNI specialist meeting on boron dilution reactivity transient"

    5 S. Kliem, "OECD PKL3 project" 2016

    6 S. Kliem, "OECD PKL2 project" 2012

    7 Boumaza, M., "Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles" 280 : 362-371, 2014

    8 Han Young Yoon, "Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code" 한국원자력학회 44 (44): 831-846, 2012

    9 Boyd, C., "Modeling approach and predictions of boron mixing in core bypass of ESBWR" 2008

    10 Cronenberg, A.W., "Memorandum to Kress, Bonaca, Uhrig, Wallis, Powers, Apostolakis: Summary of boron dilution issues and regulatory actions" U. S. Nuclear Regulatory Commission 2000

    1 J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" 한국원자력학회 42 (42): 636-655, 2010

    2 "SALOME website"

    3 윤한영, "Recent Improvements in the CUPID Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components" 한국원자력학회 46 (46): 655-666, 2014

    4 OECD, "Proceedings of the OECD/NEA/CSNI specialist meeting on boron dilution reactivity transient"

    5 S. Kliem, "OECD PKL3 project" 2016

    6 S. Kliem, "OECD PKL2 project" 2012

    7 Boumaza, M., "Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles" 280 : 362-371, 2014

    8 Han Young Yoon, "Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code" 한국원자력학회 44 (44): 831-846, 2012

    9 Boyd, C., "Modeling approach and predictions of boron mixing in core bypass of ESBWR" 2008

    10 Cronenberg, A.W., "Memorandum to Kress, Bonaca, Uhrig, Wallis, Powers, Apostolakis: Summary of boron dilution issues and regulatory actions" U. S. Nuclear Regulatory Commission 2000

    11 Jayaraju, S.T., "Large eddy simulation for an inherent boron dilution transient" 262 : 484-498, 2013

    12 Rohde, U., "Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor" 237 : 1639-1655, 2007

    13 Hagen, E.W., "Evaluation of events involving unplanned boron dilutions in nuclear power plants" U. S. Nuclear Regulatory Commission 1982

    14 FZR, "European project FLOMIX-R:Forschungszentrum Rossendorf, The European project FLOMIX-R: description of the slug mixing and buoyancy related experiment at the different test facilities" FZR 2005

    15 정재준, "DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID" 한국원자력학회 42 (42): 279-296, 2010

    16 Do, S.J., "CUPID2.2 Code Mathematical Models and Solution Methods" Korea Atomic Energy Research Institute 2018

    17 Dury, T.V., "CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies" 238 : 577-589, 2008

    18 Nuclear Energy Agency, "Best Practice Guideline for the Use of CFD in Nuclear Reactor Safety Application-Revision" OECD NEA 2015

    더보기

    동일학술지(권/호) 다른 논문

    분석정보

    View

    상세정보조회

    0

    Usage

    원문다운로드

    0

    대출신청

    0

    복사신청

    0

    EDDS신청

    0

    동일 주제 내 활용도 TOP

    더보기

    주제

    연도별 연구동향

    연도별 활용동향

    연관논문

    연구자 네트워크맵

    공동연구자 (7)

    유사연구자 (20) 활용도상위20명

    인용정보 인용지수 설명보기

    학술지 이력

    학술지 이력
    연월일 이력구분 이력상세 등재구분
    2027 평가 재인증평가 신청대상 (재인증)
    2021-01-01 등재 등재학술지 유지 (재인증) KCI등재
    2018-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2015-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2011-01-01 등재 등재 1차 FAIL (등재유지) KCI등재
    2009-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2006-01-01 등재 등재학술지 선정 (등재후보2차) KCI등재
    2005-06-16 학술지명변경 외국어명 : Jpurnal of Computatuonal Fluids Engineering -> Korean Society of Computatuonal Fluids Engineering KCI등재후보
    2005-01-01 등재 등재후보 1차 PASS (등재후보1차) KCI등재후보
    2004-01-01 등재 등재후보 1차 FAIL (등재후보1차) KCI등재후보
    2002-07-01 등재 등재후보학술지 선정 (신규평가) KCI등재후보
    더보기

    학술지 인용정보

    학술지 인용정보
    기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
    2016 0.2 0.2 0.19
    KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
    0.16 0.15 0.405 0.05
    더보기

    이 자료와 함께 이용한 RISS 자료

    나만을 위한 추천자료

    해외이동버튼