MELCOR Verification, Benchmarking, and Applications experience at BNL [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: (17 pages) : digital, PDF file
- Additional Creators:
- Brookhaven National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- This paper presents a summary of MELCOR Verification, Benchmarking and Applications experience at Brookhaven National Laboratory (BNL), sponsored by the US Nuclear Regulatory Commission (NRC). Under MELCOR verification over the past several years, all released versions of the code were installed on BNL's computer system, verification exercises were performed, and defect investigation reports were sent to SNL. Benchmarking calculations of integral severe fuel damage tests performed at BNL have helped to identify areas of modeling strengths and weaknesses in MELCOR; the most appropriate choices for input parameters; selection of axial nodalization for core cells and heat structures; and workarounds that extend the capabilities of MELCOR. These insights are explored in greater detail in the paper, with the help of selected results and comparisons. Full plant applications calculations at BNL have helped to evaluate the ability of MELCOR to successfully simulate various accident sequences and calculate source terms to the environment for both BWRs and PWRs. A summary of results, including timing of key events, thermal-hydraulic response, and environmental releases of fission products are presented for selected calculations, along with comparisons with Source Term Code Package (STCP) calculations of the same sequences. Differences in results are explained on the basis of modeling differences between the two codes. The results of a sensitivity calculation are also shown. The paper concludes by highlighting some insights on bottomline issues, and the contribution of the BNL program to MELCOR development, assessment, and the identification of user needs for optimum use of the code.
- Report Numbers:
- E 1.99:bnl-nureg-48542
E 1.99: conf-921007--21
- Published through SciTech Connect.
20. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1992.
- Funding Information:
View MARC record | catkey: 14361081