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- W1451655 abstract "The SCDAP/RELAP5 computer code 1.2 is designed to describe the overall reactor coolant system thermal-hydraulic response, core damage progression, and, in combination with VICTORIA, fission product release and transport during severe accidents up to the point of reactor vessel or system failure. The code is being developed at the Idaho National Engineering Laboratory (INEL) under the primary sponsorship of the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. SCDAP/RELAP5 has been under development at the INEL since the early 1980s and embodies much of what has been learned about the in-vessel phase of severe accidents in light water reactors. Although the behavior of the damaged core during reflood or after large debris beds have been formed is an active area of research, a number of important lessons have been learned about SCDAP/RELAP5 in particular, and severe accident modeling in general. For example, the accuracy of the code for the initial stages of core heatup and melting has been established in terms of parameters such as peak core temperature, hydrogen production, and initial loss of fuel assembly geometry through comparisons with a wide range of experiments. At the same time, critical models and their expected uncertainties have alsomore » been identified through detailed plant calculations and comparisons with data and other models. In the balance of this paper, some of these lessons will be discussed.« less" @default.
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- W1451655 date "1994-12-31" @default.
- W1451655 modified "2023-09-23" @default.
- W1451655 title "Lessons learned from the development and assessment of SCDAP/RELAP5" @default.
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