Actions for Melcor benchmarking against integral severe fuel damage tests [electronic resource].
Melcor benchmarking against integral severe fuel damage tests [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1995.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy - Physical Description
- pages 2,349-2,358 : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the U.S. Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC to provide independent assessment of MELCOR, and a very important part of this program is to benchmark MELCOR against experimental data from integral severe fuel damage tests and predictions of that data from more mechanistic codes such as SCDAP or SCDAP/RELAP5. Benchmarking analyses with MELCOR have been carried out at BNL for five integral severe fuel damage tests, namely, PBF SFD 1-1, SFD 14, and NRU FLHT-2, analyses, and their role in identifying areas of modeling strengths and weaknesses in MELCOR.
- Report Numbers
- E 1.99:nureg/cp--0142-vol.3
E 1.99: conf-950904--vol.3
conf-950904--vol.3
nureg/cp--0142-vol.3 - Subject(s)
- Note
- Published through SciTech Connect.
09/01/1995.
"nureg/cp--0142-vol.3"
" conf-950904--vol.3"
"TI95017079"
7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995.
Madni, I.K. [Brookhaven National Lab., Upton, NY (United States)].
View MARC record | catkey: 23769990