Muse - 4 Benchmark Calculations Using Mcnp - 4 C and Different Nuclear
نویسندگان
چکیده
Current calculation methods and nuclear data are well validated for conventional nuclear reactor systems. However there is a further need for validating the computational tools and the nuclear data for ADS applications. The OECD/NEA, in co-operation with CIEMAT (Spain) and CEA (France), therefore launched a benchmark based on the MUSE-4 experiments being carried out at Cadarache, France, to simulate the neutronics of a source-driven sub-critical system. This paper summarises the calculated results of the MUSE-4 benchmark obtained from the Monte Carlo code MCNP (Version 4Ca) using different nuclear data evaluations, and shows the sensitivity of the requested results with regard to the nuclear data used. All the calculated results will be compared against measured data after the completion of the experiments foreseen for the end of 2003.
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