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SCDAP/RELAP5 is an integrated, mechanistic computer code that models the progression of severe accidents in light-water-reactor nuclear power plants. The entire spectrum of in-vessel severe accident phenomena, including reactor-coolant-system thermal-hydraulic response, core heatup, degradation and relocation, and lower-head thermal loads, is treated in SCDAP/RELAP5 in a unified framework for both boiling water reactors and pressurized water reactors. Recent applications of the code include determining the initial condition for the direct containment heating issue and steam generator tube integrity studies under various severe-accident scenarios. Because the SCDAP/RELAP5 model development effort has reached an advanced state, efforts for a systematic code assessment for separate and integral effects are deemed necessary. However, the resources required to perform this task are large. A prudent approach to fostering code development and maturation is to coordinate the individual assessment efforts of the SCDAP/RELAP5 user community. While retaining individual control over assessment resources, each organization using the SCDAP/RELAP5 code could work with the other users to broaden the assessment coverage and minimize duplication. |
In recognition of these considerations, the Nuclear Regulatory Commission (NRC) has initiated the SCDAP/RELAP5 Cooperative Assessment Program (SR5CAP), a vehicle for coordinating and standardizing the assessment practices of the various SCDAP/RELAP5 users. In addition, the user community will have a forum to:
An initial SR5CAP "start-up" meeting will take place in conjunction with the Cooperative Severe Accident Research Program (CSARP) meeting to be held in May 1997. At this first SR5CAP meeting, draft SR5CAP policies and procedures (which incorporate SR5CAP participant comments) will be prepared. The NRC will review and modify these documents and then send them to the SR5CAP participants for further review and comments.
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