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Characteristics of the Integrated Steam Generators for a Liquid Metal Reactor  

Sim Yoon Sub (Korea Atomic Energy Research Institute)
Kim Eui Kwang (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.36, no.2, 2004 , pp. 127-141 More about this Journal
Abstract
Various types of integrated steam generators, which integrate IHTS and a steam generator into a single unit of equipment for an LMR, were analyzed using an analytic solution with some simplification. The analysis showed that the undesirable reversed heat transfer, of which occurrence was previously observed only in an integrated single-region bundle type, can also occur in an integrated double-region bundle type. The mechanism of the reversed heat transfer occurrence in the double-region type is explained and it is shown the mechanism in the double-region type is completely different from that in the single-region type. Based on this finding, a method for preventing the aforementioned heat transfer is suggested. The performance of the four types of the integrated steam generators is assessed. For this assessment, a SG is actually designed for each type and the optimization in the geometric parameters and flow rate are optimized.
Keywords
LMR; SG; tube bundle configuration; integrated; separated; optimization; heat transfer;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
1 Khalil H. et aI, 'Preliminary Assessment of the BREST Reactor Design and Fuel Cycle Concept', Generation IV-Submitted Reactor System Concepts-TWG3, M16, ANL, April(2001)
2 ANL (ed.), Gen IV Roadmap, Submitted Reactor System Concepts, TWG3 ( 2001)
3 Kinoshita I. at aI, 'Fundamental Heat Transfer Characteristics of a Direct Contact Steam Generator for Fast Breeder Reactor' , $3^rd$ JSME/ASME Joint lnt. 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' , $10^th$ Pacific Basic Nuclear Conf., Kobe, Japan, pp.769-778 (1996)
5 Kim S.O. et aI, '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 Sim Y.S. et aI, 'A New LMR SG with a Double Tube Bundle Free from SWR', J. of KNS, Vol.35, No.6, pp. 571-591, Dec.(2003)   과학기술학회마을
7 Kim Y.S. et aI, 'Modeling of a Once-Through Helical Coil Steam Generator of a Superheated Cycle for Sizing Analysis' , Proc. of KNS Fall Meeting, (1997)   과학기술학회마을
8 Hahn D.H. et aI, KALIMER Conceptual Design Report, KAERI/TR-2204/2002, KAERI, (2002)
9 Adamov E.O.(ed.), Naturally Safe Lead Cooled Fast Reactor for Large-Scale Nuclear Power, Moscow, Russia (2001)