Nuclear Engineering and Technology

  • 제42권6호
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  • Pages.636-655
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  • 2010
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY

  • Jeong, J.J. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Yoon, H.Y. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Park, I.K. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Cho, H.K. (Korea Atomic Energy Research Institute (KAERI))
  • 투고 : 2010.12.06
  • 발행 : 2010.12.31
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초록

A thermal-hydraulic code, named CUPID, has been being developed for the realistic analysis of transient two-phase flows in nuclear reactor components. The CUPID code development was motivated from very practical needs, including the analyses of a downcomer boiling, a two-phase flow mixing in a pool, and a two-phase flow in a direct vessel injection system. The CUPID code adopts a two-fluid, three-field model for two-phase flows, and the governing equations are solved over unstructured grids with a semi-implicit two-step method. This paper presents an overview of the CUPID code development and assessment strategy. It also presents the code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER.

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피인용 문헌

  1. Preliminary Analysis of the CANDU Moderator Thermal-Hydraulics using the CUPID Code vol.21, pp.4, 2012, https://doi.org/10.5855/ENERGY.2012.21.4.419
  2. Assessment of the two-phase flow models in the CUPID code using the downcomer boiling experiment vol.49, pp.1, 2012, https://doi.org/10.1080/18811248.2011.636560
  3. VERIFICATION OF TURBULENCE AND NON-DRAG INTERFACIAL FORCE MODELS OF A COMPUTATIONAL MULTI-FLUID DYNAMICS CODE vol.18, pp.2, 2013, https://doi.org/10.6112/kscfe.2013.18.2.099
  4. Numerical Evaluation of the Cooling Performance of a Core Catcher Test Facility vol.22, pp.1, 2013, https://doi.org/10.5855/ENERGY.2013.22.1.008
  5. Preliminary Thermal-Hydraulic Analysis of the CANDU Reactor Moderator Tank using the CUPID Code vol.23, pp.4, 2014, https://doi.org/10.5855/ENERGY.2014.23.4.095
  6. COMPONENT AND SYSTEM MULTI-SCALE DIRECT-COUPLED CODE IMPLEMENTATION USING CUPID AND MARS CODES vol.21, pp.3, 2016, https://doi.org/10.6112/kscfe.2016.21.3.089
  7. Domain decomposition parallel computing for transient two-phase flow of nuclear reactors vol.30, pp.5, 2016, https://doi.org/10.1007/s12206-016-0411-3
  8. Comparative study of the two-fluid momentum equations for multi-dimensional bubbly flows: Modification of Reynolds stress vol.31, pp.1, 2017, https://doi.org/10.1007/s12206-016-1223-1
  9. Assessment of the CUPID Code for Bubbly Flows in Horizontal Pipes pp.1943-7471, 2018, https://doi.org/10.1080/00295450.2018.1475193