AbstractThis paper briefly describes the codes used for International Thermonuclear Experimental Reactor (ITER) safety analysis, including some information on their validation status, and summarizes some examples of validation and verification (V&V). V&V information is provided for the codes involved in accident analyses dealing with water coolant ingress into the vacuum vessel. Results obtained by the MELCOR and INTRA codes, and the ISAS system, are compared with the test results of the integrated ICE facility simulating water coolant ingress into the vacuum vessel. Benchmark calculation results of the MELCOR, INTRA, and ISAS were compared with the results from other codes like PAX, CONSEN, TRAC-BF1, CATHARE.
Validation of numerical codes for the analysis of plasma discharges