본문 바로가기
HOME> 논문 > 논문 검색상세

논문 상세정보

Journal of the Korean Nuclear Society = 원자력학회지 v.35 no.6, 2003년, pp.566 - 580   피인용횟수: 1

A New LMR SG with a Double Tube Bundle Free from SWR

Sim Yoon-Sub    (Korea Atomic Energy Research Institute   ); Kim Seong-O    (Korea Atomic Energy Research Institute   ); Kim Eui Kwang    (Korea Atomic Energy Research Institute   ); Hahn Do Hee    (Korea Atomic Energy Research Institute  );
  • 초록

    To resolve the concern of the SWR possibility in LMR and improve the economic feature of LMR, relative performance of various SG designs using a double tube bundle configuration is evaluated and a new SG design concept is proposed. The new steam generator design houses two tube bundles that are functionally different and its tube bundle region is radially divided into two. It prevents the occurrence of sodium water reaction while sodium is still used as the coolant for the primary heat transport system. The feasibility of the SG with a double tube bundle for actual use in an LMR plant is evaluated by setting up the skeleton of the NSSS for various possible configurations of the SG tube bundles. The evaluation revealed the relative advantages and disadvantages of the configurations and the new SG design concept performs good and can be actually used in an LMR plant.


  • 주제어

    LMR .   SWR .   SG .   tube bundle configuration .   double .   performance .   evaluation.  

  • 참고문헌 (9)

    1. Adamov E.O.(ed.), Naturally Safe Lead Cooled Fast Reactor for Large-Scale Nuclear Power, Moscow, Russia (2001) 
    2. ANL (ed.), Gen IV Roadmap, Submitted Reactor System Concepts, TWG3 (2001) 
    3. Kinoshita I. at al, 'Fundamental Heat Transfer Characteristics of a Direct Contact Steam Generator for Fast Breeder Reactor' , 3rd JSME/ASME Joint Int. Conf. on Nuclear Eng., Kyoto, Japan, Vol.1, pp.11-16 (1995) 
    4. Miyazaki K, et al, 'Advanced IHX-SG combined FBR System Designs and Basic Experiments' , 10th Pacific Basic Nuclear Conf., Kobe, Japan, pp.769-778 (1996) 
    5. Kim S.O., et al, 2003. 'Evaluation of New Design Concepts for Steam Generators in Sodium Cooled Liquid Metal Reactor' , J. of KNS, Vol.35, No.2, pp.121-132, April (2003) 
    6. Horiike H., et al, 'Advanced Intermediate heat Exchanger for FBR' , ICONE11-36293, Tokyo,Japan, April 20-23 (2003) 
    7. Hahn D.H. et al, KALIMER Conceptual Design Report, KAERI/TR-2204/2002, KAERI, (2002) 
    8. Holman J.P., Heat Transfer, McGraw-Hill Book (1986) 
    9. Philpott E.F. et al, 'The effect of Steam Cycle Conditions upon the Economics and Design of a Sodium-Cooled Fast Reactor', Session 5, Proc. of the Int. Conf. organized by British Nuclear Energy Society in London (1977) 
  • 이 논문을 인용한 문헌 (1)

    1. 2004. "" Journal of the Korean Nuclear Society = 원자력학회지, 36(2): 127~141     

 저자의 다른 논문

  • Sim Yoon Sub (1)

    1. 2004 "Characteristics of the Integrated Steam Generators for a Liquid Metal Reactor" Journal of the Korean Nuclear Society = 원자력학회지 36 (2): 127~141    
  • Kim, Seong-O (9)

  • Kim Eui Kwang (1)

 활용도 분석

  • 상세보기

    amChart 영역
  • 원문보기

    amChart 영역

원문보기

무료다운로드
  • NDSL :
유료다운로드

유료 다운로드의 경우 해당 사이트의 정책에 따라 신규 회원가입, 로그인, 유료 구매 등이 필요할 수 있습니다. 해당 사이트에서 발생하는 귀하의 모든 정보활동은 NDSL의 서비스 정책과 무관합니다.

원문복사신청을 하시면, 일부 해외 인쇄학술지의 경우 외국학술지지원센터(FRIC)에서
무료 원문복사 서비스를 제공합니다.

NDSL에서는 해당 원문을 복사서비스하고 있습니다. 위의 원문복사신청 또는 장바구니 담기를 통하여 원문복사서비스 이용이 가능합니다.

이 논문과 함께 출판된 논문 + 더보기