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[en] Foil activation method is commonly used in flux and neutron spectrum measurement in nuclear reactor and other research. The effect of the thickness, type of foil material and neutron spectrum shape on the self shielding correction and activities correction on the edges of the foil have been analyzed. Also the effect of neglecting those correction factors on neutron flux and spectrum measurement were analyzed. The calculation of the correction factor has been done by using the program which had been verified for several foils. The foils used are Au, In. Cu, Co and Dy of 0.00254 cm -0.127 cm thickness and 1.27 cm diameter. The result showed that the correction factor foils were not similar due to the variation of activation cross section and neutron spectrum shape. For the neutron spectrum in RS-2 multi purpose reactor GAS using foils of 0.00254 cm thick. The effect of neglecting correction factor on thermal flux measurement for Au, In, Co and Cu were less than -6%, for Dy was about -25%. On epithermal flux measurement for Au and In were about -60%, Co and Dy was -12% and -6%, for Cu less than -2%. The effect of neglecting correction factor on spectrum measurement was the change on the neutron flux density values along neutron energy region
Source
Sudjatmoko; Karmanto, Eko Edy; Supartini, Endang (Yogyakarta Nuclear Research Center, National Nuclear Energy Agency, Yogyakarta (Indonesia)); Yogyakarta Nuclear Research Center, National Nuclear Energy Agency, Yogyakarta (Indonesia); 285 p; ISSN 0216-3128; 
; Apr 1996; p. 194-200; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan Teknologi Nuklir; Yogyakarta (Indonesia); 23-25 Apr 1996; Available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 3 tabs.; 3 figs.
; Apr 1996; p. 194-200; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan Teknologi Nuklir; Yogyakarta (Indonesia); 23-25 Apr 1996; Available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 3 tabs.; 3 figs.