UWFDM-999 Results of the Neutronics and Shielding Calculational Benchmark

ETUTITSNIYWGISOCLResultsoftheNeutronicsandShieldingCalculationalBenchmarkM.E.SawanNovember1995UWFDM-999Presented at the IAEA Advisory Group Meeting on “Completion of FENDL-1 and Startof FENDL-2”, Del Mar, CA, 5–9 December 1995.FUSION TECHNOLOGY INSTITUTEUNIVERSITY OF WISCONSINMADISON WISCONSINOONNSHINCETNOISUFRESULTS OF THE NEUTRONICS AND SHIELDINGCALCULATIONAL BENCHMARKMohamed E. SawanFusion Technology InstituteUniversity of Wisconsin-Madison1500 Engineering DriveMadison, WI 53706December 1995UWFDM-999Presented at the IAEA Advisory Group Meeting on "Completion of FENDL-1 and Start ofFENDL-2," Del Mar, CA, 5-9 December 1995.INTRODUCTIONDuring the IAEA Advisory Group Meeting on "Improved Evaluations and Integral DataTesting for FENDL" held in Garching, Germany in the period 12-16 September 1994, theWorking Group II on "Experimental and Calculational Benchmarks on Fusion Neutronics forFENDL Validation" recommended that a calculational benchmark representative of the ITER designshould be developed [1]. This benchmark problem can be used to assess the impact of transportcodes, nuclear data evaluation, nuclear data processing, and multigroup structure on the flux anddesign relevant nuclear parameters (heating, damage, gas production) in a fusion reactor relevantconfiguration. The detailed description and specifications of the neutronics and shieldingcalculational benchmark were provided to the IAEA ...