Verification and Validation of STREAM/RAST-K for PWR Analysis

다국어 초록 (Multilingual Abstract)

This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for apressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion codeRAST-K 2.0 have been developed by a computational reactor physics and experiment laboratory (CORE)of Ulsan National Institute of Science and Technology (UNIST) for an accurate two-step PWR analysis. Thecalculation modules of each code were already verified against various benchmark problems, whereasthis paper focuses on the V&V of linked code system. Three PWR type reactor cores, OPR-1000, threeloopWestinghouse reactor core, and APR-1400, are selected as V&V target plants. This code system, forverification, is compared against the conventional code systems used for the calculations in nucleardesign reports (NDRs) and validated against measured plant data. Compared parameters are as follows:critical boron concentration (CBC), axial shape index (ASI), assembly-wise power distribution, burnupdistribution and peaking factors. STREAM/RAST-K 2.0 shows the RMS error of critical boron concentrationwithin 20 ppm, and the RMS error of assembly power within 1.34% for all the cycles of all reactors.

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