DEVELOPMENT OF SHIELDING ANALYSIS METHOD FOR LARGE FAST-REACTOR SUMMARY RESULTS OF JAPANESE-AMERICAN SHIELDING PROGRAM FOR EXPERIMENTAL RESEARCH (JASPER)

All experiments planned in the JASPER, Japanese-American Shielding Pro gram for Experimental Research, had been conducted between 1986 and 19 92 under the cooperation between the U.S. Department of Energy and Pow er Reactor and Nuclear Fuel Development Corporation of Japan to obtain useful information on FBR shielding analysis accuracy. Tower Shieldin g Facility (TSF) of Oak Ridge National Laboratory was utilized for all the measurements. Results obtained from the post-experimental analyse s are summarized in this report. Both characteristics for bulk shieldi ng attenuation and streaming of neutron through configurations consist ing of several materials including boron-carbide (B4C), graphite, stai nless steel, sodium and etc. were clarified and the analysis accuracy confirmed. Prediction accuracy in both shielding property for configur ation containing fissile material and sodium activation characteristic s was confirmed. The shielding analysis system for fast reactors using a 2-dimensional discrete ordinates code as a standard has been improv ed and verified. Through those activities, useful information to be ut ilized in designing large FBR is accumulated.