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[en] The calculation of detailed radioisotopic composition in biological shield and verification with experimental results is presented. Neutron fluxes in different spatial locations in biological shield are obtained with TORT code. Libraries used with TORT code are BUGLE-96 (coupled 47 neutron groups and 20 gamma groups) and library derived from VITAMIN-B6 (coupled library with 199 neutron groups and 42 gamma groups). Isotopic composition is calculated for various irradiation intervals and also for several decay intervals from different initial irradiation intervals. Neutron fluxes obtained with TORT code are used as input for activation calculation in several locations of the biological shield. Several neutron spectrum constants from known neutron flux have to be derived before isotopic calculation. SCALE code package is used for isotopic calculation. Experimental results used for comparison are available from irradiation experiment with selected type of concrete and other materials in beam port 4 (irradiation channel 4) in TRIGA Mark II reactor. These experimental results are used for verifying the calculation models. The agreement between the measured and calculated activities is within the interval of experimental error.(author)
Source
Jencic, I.; Tkavc, M. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (Belgium); Canberra-Packard Central Europe, Schwadorf (Austria); Elmont, Krsko (Slovenia); ENCONET International, Zagreb (Croatia); Inetec, Zagreb (Croatia); NUMIP, Krsko (Slovenia); Q Techna, Krsko (Slovenia); SIAP, Maribor (Slovenia); [602 p.]; ISBN 961-6207-20-2; 
; 2002; [8 p.]; International Conference Nuclear Energy in Central Europe 2002; Kranjska Gora (Slovenia); 9-12 Sep 2002; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs., 1 tab., 5 figs.
; 2002; [8 p.]; International Conference Nuclear Energy in Central Europe 2002; Kranjska Gora (Slovenia); 9-12 Sep 2002; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs., 1 tab., 5 figs.