한국전산유체공학회지 (Journal of computational fluids engineering)

한국전산유체공학회 (Korean Society of Computational Fluids Engineering)
권호 표지
DOI QR코드

DOI QR Code

전산유체역학을 이용한 소듐-소듐 열교환기 설계코드의 검증

VALIDATION OF A DESIGN CODE FOR SODIUM-TO-SODIUM HEAT EXCHANGERS BY UTILIZING COMPUTATIONAL FLUID DYNAMICS

  • 김대희 (한국원자력연구원 SFR계통설계부) ;
  • 어재혁 (한국원자력연구원 SFR계통설계부) ;
  • 이태호 (한국원자력연구원 SFR계통설계부)
  • Kim, D. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute) ;
  • Eoh, J.H. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute) ;
  • Lee, T.H. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute)
  • 투고 : 2016.02.01
  • 심사 : 2016.03.15
  • 발행 : 2016.03.31
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

A Prototype Gen-IV Sodium-cooled Fast Reactor which is one of the $4^{th}$ generation nuclear reactors is in development by Korea Atomic Energy Research Institute. The reactor is composed of four main fluid systems which are categorized by its functions, i.e., Primary Heat Transport System, Intermediate Heat Transport System, Decay Heat Removal System and Sodium-Water Reaction Pressure Relief System. The coolant of the reactor is liquid sodium and sodium-to-sodium heat exchangers are installed at the interfaces between two fluid systems, Intermediate Heat Exchangers between the Primary Heat Transport System and the Intermediate Heat Transport System and Decay Heat Exchangers between the Primary Heat Transport System and the Decay Heat Removal System. For the design and performance analysis of the Intermediate Heat Exchanger and the Decay Heat Exchanger, a computer code was written during previous step of research. In this work, the computer code named "SHXSA" has been validated preliminarily by computational fluid dynamics simulations.

키워드

참고문헌

  1. 2009, Hahn, D., Chang J., Kim, Y.I., Kim, Y.I., Lee, C.B., Kim, S.O., Lee, J.H., Ha, K.S., Kim, B.H. and Lee, Y.B., "Advanced SFR Design Concepts and R&D Activities," Nuclear Engineering and Technology, Vol.41, No.4, pp.427-446. https://doi.org/10.5516/NET.2009.41.4.427
  2. 2012, Eoh, J.H., "Conceptual Design Report of PGSFR IHX," Korea Atomic Energy Research Institute, Internal Design Report, SFR-220-DF-462-001.
  3. 2012, Eoh, J.H., "Conceptual Design Report of PGSFR DHX," Korea Atomic Energy Research Institute, Internal Design Report, SFR-514-DF-462-001.
  4. 1982, Heisler, M.P., "Development of Scaling Requirements for Natural Convection Liquid-Metal Fast Breeder Reactor Shutdown Heat removal Test Facilities," Nuclear Science and Engineering, Vol.80, pp.347-359. https://doi.org/10.13182/NSE82-A19819
  5. 1976, Kazimi, M.S. and Carelli, M.D., "Heat Transfer Correlation for Analysis of CRBRP Assemblies," Westinghouse Report, CRBRP-ARD-0034.
  6. 1973, Graber, H. and Rieger, M., "Experimental Study of Heat Transfer to Liquid Metals Flowing In-line through Tube Bundles," Progress in Heat and Mass Transfer, Vol.7, p.151.
  7. 1980, Olson, R.M., Essentials of Engineering Fluid Mechanics(4th ed.), Harper & Row, Publishers, New York.
  8. 1986, Idelchik I.E., Handbook of Hydraulic Resistance(2nd ed.), Hemisphere Publishing Corporation.
  9. 1990, Todreas N.E. and Kazimi M.S., Nuclear Systems (I), Hemisphere Publishing Corporation, New York, USA.
  10. 2012, CD-adapco, USER GUIDE, STAR-CCM+ Version 7.04.011.