Development and Assessment of the COBRA/RELAP5 Code.

• JEONG Jae-Jun

  Korea Atomic Energy Research Institute (KAERI)

• SIM Suk Ku

  Korea Atomic Energy Research Institute (KAERI)

• LEE Sang Yong

  Korea Power Engineering Company, Inc. (KOPEC)

Bibliographic Information

Other Title

• Development and Assessment of the COBRA

Abstract

<BR>The COBRA/RELAP5 code has been developed to combine the realistic three-dimensional reactor vessel model of COBRA-TF with RELAP5/MOD3.2, thus to produce an advanced system analysis code with a multidimensional thermal-hydraulic module. This paper provides the integration scheme of the two codes. The results of developmental assesments are also provided, which include single channel tests, manometric flow oscillation problem, THTF Test 105, and LOFT L2-3 large break loss-of-coolant experiment. From the single channel tests, the integration scheme was proven to be valid. Other simulation results showed good agreement with the experimental data. The computational speed was also satisfactory. Therefore, the assessment confirmed that the COBRA/RELAP5 code can be a promising tool for analysis of complicated, multimensional, two-phase flow system transients.

Journal

• Journal of Nuclear Science and Technology

  Journal of Nuclear Science and Technology 34 (11), 1087-1098, 1997

  Atomic Energy Society of Japan

Keywords

• best-estimate system codes
• computer codes
• COBRA-TF
• RELAP5/MOD3.2
• COBRA/RELAP5
• code integration
• three-dimensional thermal-hydraulic module
• interprocess communication
• parallel processing
• accuracy

Details

• CRID: 1390282679070693632
• NII Article ID: 10002078440
• NII Book ID: AA00703720
• DOI: 10.3327/jnst.34.1087
• COI: 1:CAS:528:DyaK1cXhsVyktg%3D%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL BIB ID: 4346186
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4346186
• Text Lang: en
• Data Source:
  • JaLC
  • NDL
  • Crossref
  • CiNii Articles
• Abstract License Flag: Disallowed