Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
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Development of the Unified Version of COBRA/RELAP5

  • J. J. Jeong (Korea Atomic energy Research Institute(KAERI)) ;
  • K. S. Ha (Korea Atomic energy Research Institute(KAERI)) ;
  • B. D. Chung (Korea Atomic energy Research Institute(KAERI)) ;
  • Lee, W. J. (Korea Atomic energy Research Institute(KAERI)) ;
  • S. K. Sim (Korea Atomic energy Research Institute(KAERI))
  • Published : 1997.10.01
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Abstract

The COBRA/RELAPS code, an integrated version of the COBRA-TF and RELAP5/MOD3 codes, has been developed for the realistic simulations of complicated, multi-dimensional, two-phase, thermal-hydraulic system transients in light water reactors. Recently, KAERA developed an unified version of the COBRA/RELAP5 code, which can run in serial mode on both workstations and personal computers. This paper provides the brief overview of the code integration scheme, the recent code modifications, the developmental assessments, and the future development plan.

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