USING CFD TO ANALYZE NUCLEAR SYSTEMS BEHAVIOR [electronic resource] : DEFINING THE VALIDATION REQUIREMENTS
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2012. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Additional Creators:
- Idaho National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- A recommended protocol to formulate numeric tool specifications and validation needs in concert with practices accepted by regulatory agencies for advanced reactors is described. The protocol is based on the plant type and perceived transient and accident envelopes that translates to boundary conditions for a process that gives the: (a) key phenomena and figures-of-merit which must be analyzed to ensure that the advanced plant can be licensed, (b) specification of the numeric tool capabilities necessary to perform the required analyses—including bounding calculational uncertainties, and (c) specification of the validation matrices and experiments--including the desired validation data. The result of applying the process enables a complete program to be defined, including costs, for creating and benchmarking transient and accident analysis methods for advanced reactors. By following a process that is in concert with regulatory agency licensing requirements from the start to finish, based on historical acceptance of past licensing submittals, the methods derived and validated have a high probability of regulatory agency acceptance.
- Published through SciTech Connect., 09/01/2012., "inl/con-12-27100", Experimental Validation and Application of CFD and CMFD Codes in Nuclear Reactor Technology,Daejeon, Korea ,09/10/2012,09/12/2012., and Richard Schultz.
- Funding Information:
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