Nuclear fuel rod behavior during LOFT experiment L2-2 [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1979. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 16 : digital, PDF file
- Additional Creators:
- United States. Department of Energy and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The Loss-of-Fluid Test (LOFT) Program is providing data to evaluate analytical models used to predict the thermal-hydraulic and fuel rod response of a pressurized water reactor (PWR) under loss-of-coolant accident (LOCA) conditions. The fuel rod response for the first nuclear loss-of-coolant experiment (LOCE), LOCE L2-2, is summarized.
- Published through SciTech Connect., 01/01/1979., "conf-790646--3", International colloquium on irradiation for reactor safety programmes, Petten, Netherlands, 25 Jun 1979., Tolman, E. L.; Niebruegge, D. A.; Prassinos, P. G., and Idaho National Engineering Lab., Idaho Falls (USA)
- Funding Information:
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